W3P85-1466, Semiannual Radioactive Effluent Release Rept for 850304-0630
| ML20135D482 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/30/1985 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| W3P85-1466, NUDOCS 8509160072 | |
| Download: ML20135D482 (165) | |
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Semiannual Radioactive Effluent Release Report March 4, 1985 - June 30, 1985 Waterford 3 SES Louisiana Power and Light na" M A S TBa' R gL,4 I/
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TABLE OF CONTENTS 1.0 SCOPE 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 e 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES 8.0 RELATED INFORMATION 8.1 Chang (s to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 8.5 Violations of Radioactive Liquid Waste Sampling and Analysis Program, Table 4.11-1 9.0 TABLES 10.0 ATTACHMENTS W350004H- 1
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1.0 SCOPE This Semi-Annual Release Report is submitted as required by Louisiana Power and Light's Waterford 3 Technical Specification 6.9.1.8. It covers the period from initial criticality on March 4, 1985 through June 30, 1985.
Included in this report is a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant.
. The summary of meteorological data and the assessment of radiation doses due to the release of liquid and gaseous radioactive effluents for the reporting period will be included in the Semi-Annual Radioactive Effluent Release Report to be submitted within 60 days after January 1,1986.
Information in this report is presented in the format outlined in :
Appendix B of Regulatory Guide 1.21. ,
, Other required information in this report includes: (1) explanation of why certain instrumentation was not restored to operable status within the time specified in the ACTION Statement, as per Waterford 3 SES Technical Specification 3/4.3.3.11; (2) changes to the Process Control Program and Off-Site Dose Calculation Manual; and, (3) a report of Deviation from Technical Specification Table 4.11-1.
s 2.0 SUPPLEMENTAL INFORMATION P
2.1 Regulatory Limits Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents. t
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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 the site areas at or 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.
2.1.2 Iodines; Particulates, Half Lives > 8 Days; and Tritium 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 1500 ores /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 area to any organ and, W350004H 3-1-
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- b. During any calendar year: Less than or equal to 15 mrem to any organ.
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 10CFR 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-4 pCi/ml total activity.
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 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.
.2.2. Maximum Permissible Co'ncentrations 2.2.1 . Fission and Activation Gases;-Iodines; and Particulates, Half Lives > 8 Days-
-For gaseous effluents, maximum permissible' concentrations are =
not directly used in release rate' calculations since the~
~
applicable-limits are ' expressed in terms of dose rate at the site boundaty.
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2.2.2 Liquid Effluents .
I The maximum permissible concentration (MPC) values specified f in 10CFR20, Appendix B, Table II, Column 2 are used as the -
permissible concentrations of liquid radioactive effluents at '
l the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in i liquid effluents. ;
i 2.3 Average Energg This is not applicable to Waterford 3 SES's radiological effluent technical specifications. I 2.4 Measurements and Approximations of Total Radioactivity '
The quantification of radioactivity in liquid and gaseous effluents was accomplisted by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.11-1 and 4.11-2 of the' Waterford 3 SES Plant Technical Specifications (see Attachments 1 and 2).
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2.4.1 Fission and Activation Gases (Noble Gases)
For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was '
calculated according to the following equatio1:
GR = Average Weekly Noble Gas Monitor Reading Mcnitor Reading During Noble Gas Sampling W350004H 5
2
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The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the i previous week. For gas decay tank and cantainment purge !
batch releases, a gas grab sample was analyzed prior to <
release to determine noble gas concentrations in the batch.
In all cases the measured total radioactivity in gaseous effluents was determined from measured concentrations of each I radionuclide present and the total volume discharged. ;
2.4.2 Iodines and Particulates For continuous releases, iodines and particulates were l sampled using a continuous sampler. Each week the charcoal cartridge and particulate filter were analyzed for gamma i e
emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volume discharged were'used to calculate the previous week's activity released.
Composites of the continuous particulate' samples were ,
analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes). Gross alpha was measured weekly using gas flow proportional counting techniques. The i determined activities were used to estimate effluent ;
concentrations in subsequent releases until the next scheduled analysis was performed.
1 Grab tritium samples for continuous and batch releases were ;
P analyzed monthly. The determined concentrations were used to j
estimate tritium activity in subsequent releases until the next scheduled analysis was performed.
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4 2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release.
For both continuous and batch releases, Sr-89, Sr-90, and Fe-55 composite samples were analyzed quarterly by a contract laboratory (Teledyne Isotopes). Tritium and gross alpha composite samples were analyzed monthly using liquid scintillation and gas flow proportional techniques respectively.
For radionuclides analyzed in composite samples, the measured concentrations of the previous composite were used in determining concentrations in liquid effluents.
The measured total radioactivity in liquid effluent releases is determined from the measured concentrations of each radionuclide present and the total volume of the effluent discharged.
2.5 Batch Releases The Summarization of information for gaseous and liquid batch releases is included in Table 1.
i i
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2.6 Abnormal Releases On April 3 and 4, 1985, an unplanned release was made to the Waterford 3 metal waste pond as a result of slightly radioactive steam generator blowdown being diverted to that point. This pond lies within the restricted area; therefore, the total activity was not included in Table 2A or Table 2B as a release "from the site boundary". Maximum concentrations during the release were 3.5 E-6 pCi/ml Na-24 and 3.9 E-7 pCi/ml I-133. No other radionuclides were detected. The maximum total activity discharged to the pond was 0.72 Ci Na-24 and 0.04 Ci I-133. Both of these nuclides have half short lives (20.8 hr for I-133 and 15 hr for Na-24).
3.0 GASEOUS EFFLUENTS ,
The quantities of radioactive material released in gaseous effluents are summarized in Tables IA, IB, and IC. Note that there are no elevated rrleases at Waterford 3 SES.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.
5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3.
6.0 METEOROLOGICAL DATA The summary of hourly meteorological data for this reporting period will be included in the Semi-annual Effluent Release Report to be submitted
. within 60 days after January 1, 1986.
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.7.0 ASSESSMENT OF DOSES i.
The-summary of doses from gaseous and liquid effluents for this reporting $
j period.will be included in the Semi-annual Effluent Release Report to be l submitted within 60 days after January 1, 1986. [
8.0 :RELATED INFORMATION '
l 8.1 Changes to the Process Control Program 1
i On May 30, 1985, Revision 1 of the Waterford 3 Process Control i Program was reviewed at Plant Operations Review Committee (PORC) meeting 85-104 and approved by the Plant Manager for issue on ' i, June 5, 1985. This revision was the first revision / change for the (
- previously NRC approved Revision 0. A copy of this revision is [
' included as Attachment 3. 1 i f F
This revision was made te remove non-applicable referenced plant and vendor procedures. A summarization of the changes to the Process ;
Control Program is listed below: -
i 8.1.1 Reference 2.1.7, Nuclear Operations Quality Assurance Manual, ;
t Section 2, Chapter 6 was changed to Nuclear Operations ,
Management Manual (section VI, Chapter 5).
1 I
4 The change was necessary because- the Nuclear Operations :
Quality Assurance Manual was incorporated into the Nuclear :
Operations Management Manual.
l 8.1.2 Reference 2.2.1, PS-5, 3-037B, NUS Process Services I Corporation, Topical Report on Radwaste Solidification 4 System, Rev. O was deleted because it was the same report as
, Reference 2.2.2, TR002, NUS Process Services Corporation, Topical Report on 10CFR61, Qualified Radioactive Waste Forms, May 1984. .
W350004H. 9 pp -e- w-1,=-w w op r-r-e,-n-_-*w+e,m~rym=vm-v-w-=-e 4mv'-m+re-- m
8.1.3 Reference 2.2.6, KN-R1109, Westinghouse /Hittman Nuclear, Inc.
Topical Report on Radwaste Solidification System (cement),
Rev. 4 was deleted because this is a report for inplant radwaste solidification system installed at another utility.
8.1.4 Section 4.6.1 was changed to read, "The Plant Quality Manager is responsible for the review of Plant Process Control Program procedures," in order to clarify the responsibilities of the Plant Quality Manager.
8.1.5 Section 5.1.1 and 5.24.1.1 were changed to reflect the proper reference numbers.
8.2 Changes to the Offsite Dose Calculation Manual On February 7, 1985, Revision 4 of the Waterford 3 Offsite Dose Calculation Manual was reviewed at Plant Operating Review Committee (PORC) meeting 85-28, and approved by the Plant Manager for issue on
, February 18, 1985. This revision was the first revision / change for the previously NRC approved Revision 3.
The changes were made to correct typographical errors, clarify passages or equations, incorporate Technical Specification changes, and reflect the 1984 Annual Land Use Census. A copy of the Offsite Dose Calculation Manual with change bars is included as Attachment 4.
A summarization of the changes to the document is listed below:
1 8.2.1 Section 8.1 was changed to include the location of the visitor center.
18.2.2- Section 8.4 was changed to indicate that modifications to the radwaste systems should be documented in the ODCM.
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8.2.3 Section 8.5.1.1.D was added to accommodate changes in Technical Specification Table 4.11-1, which now allows batch radioactive effluents to be discharged from the waste tanks.
8.2.4 Wording of Section 8.5.1.2 was changed for clarification.
i 8.2.5 A statement dealing with continuous release permits was added to Section 8.5.2.3 to address radionuclide accountability for releases from the Main Condenser Evacuation System (MCES). !
8.2.6 Section 8.8 was changed to indicate that test determining liquid waste tank recirculation times have been performed.
I i 8.2.7 Changes were made to Section 8.10.1.2 to clarify the 1 definitions of variables D and P gt, l OI 8.2.8 The definitions of (X/Q)jgv-was added to Section 8.11.1.2 to clarify equations. .
8.2.9 Equations in Sections 8.12.1.1, 8.12.1.2, 8.12.2.1, and 8.12.2.2 were changed to clarify variable definitions.
8.2.10 Table 1 was changed to reflect milk cows, goats, vegetable gardens, and residences identified in the 1984 Land Use Census. -
8.2.11 Changes to Table 2 include correction of Analysis and Frequency for Drinking and Surface Water, designation of new milk sampling locations, breakdown of Food. Products into Food Products and Broad Leaf and identification of new Broad Leaf Sample Location at 10 miles.
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8.2.12 Changes to Table 3 include better descriptions of actual TLD locations, designation of all control locations with an asterisk, the breakdown of Food Products Locations into Food Products and Broad Leaf, the identification of a new Broad Leaf Control Location and deletions and additions to the Milk Sampling Locations.
8.2.13 Typographical errors were corrected on Table 4.
8.2.14 Figures 1and2werechangedtoreflectthechangesdescribed for Table 3.
8.2.15 Table 9 was changed to reflect the results of the 1984 Annual Land Use Census as described for Table 1.
None of these described changes actually changed dose, dose rate, or setpoint calculations. Variables and equations were modified in a descriptive manner only. The accuracy or reliability of these equations was not reduced.
8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, . Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1. Milk is collected, when available, from the control location and two identified sampling locations as indicated in ODCM, Table 2 and Table 3.
8 . <4 Report of Technical Specification Required Instrument Inoperability Technical Specification, Limiting Condition for Operation (LCO),
3.3.3.11 requires the reporting in the Semi-annual Effluent Release Report of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement.
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8.4.1 Monitor
Radiation Monitor PRM-IRE-0648 (Gaseous Waste Management System)
Period of Inoperability: 3/29/85 - 4/24/85 (26 days)
Time Required by Technical Specifications to Restore Operability: 14 days Cause of Inoperability:
Water leakage into the monitor necessitated locking closed valves in the system that would normally remain open to relieve pressure on the detector. The resulting overpres-surization in the monitor caused the detector window to develop a tear.
Reason In' operability Not Restored Within Allotted Time:
No spare windows were available on site requiring a replacement to be ordered. Upon receipt of the part, the monitor could not be restored to OPERABLE status within the required time.
8.4.2 Monitor
W'aste Gas Holdup System Hydrogen Monitor and Oxygen Monitors Period of Inoperability: 3/21/85 - 6/31/85 (i.t end of reporting period conitors were still inoparabic) i Time Required by Technical Specifications to Restore Operability: 14 days W350004H 13
_ _ _ _ - _ _ _ _ - _ _ - _ _ - _ - _ _ _ - _ _ _ . ._____ _ _ =--_-____-__---_____-__- _--___-___--_ _ _- _ ___- _ - - __-_-_-_ _ - _ :
Cause of Inoperability:
Due to design problems excess amounts of moisture were allowed to leak into both the Beckman 0 and Delphi H and 0 2 2 2 analyzer systems.
Reason Inoperability Not Restored Within Allotted Time:
Extensive hours were spent attempting to restore these analyzers to operable status. Several analyzer cells were replaced, the solenoid and regulator were repaired, and the sample pump was both repaired and replaced. After these efforts failed to return the monitor to service, a station modification was initiated to replace the analyzer cells with less moisture sensitive models and to completely redesign the sample line condensate drain system. _These extensive modifications will require greater than 14 days to complete.
8.5 Violations of Radioactive Liquid Waste Sampling and Analysis Program, Table 4.11.-1 8.5.1 Liquid Release Type: Turbine Building Industrial Waste Sumps Sampling Frequency: Weekly Grab Sample Miricum Analysis Frequency: Monthly Type of Activity Analysis: H-3 and Gross Alpha W350004H 14
c; Description of Violation:
Weekly sampling of the Turbine Building Industrial Waste Sumps is required when activity exists in the secondary system and for four subsequent weeks. The samples are to be composited and analyzed for gross alpha and H-3 monthly. The samples collected for April- and May 1985 were not analyzed for tritium or gross alpha in the required time period. The samples were composited and analyzed when preparing quarterly composite samples on 7/3/85.
9.0 TABLES 1 Batch Release Summary 1A Semi-annual Summation of all Releases by Quarter - All Airborne Effluents i IB Semi-annual Airborne Continuous Elevated and Ground Level Releases 1C Semi-annual Airborne Batch Elevated and Ground Level Releases 2A Semi-annual Summation of All Releases by Quarter - All Liquid Effluents 2B Semi-annual Liquid Continuous and Batch Releases 3 Solid Waste Shipped Offsite for Disposal 10.0 ATTACHMENTS
- 1. Technical Specification Table 4.11-1
- 2. Technical Specification Table 4.11-2
- 3. . Process Control Program, RW-1-210, Revision 1 ,
- 4. Offsite Dose Calculation Manual, HP-1-230, Revision 4 W350004H 15 h . _ _ _ _ . . _ _ _ _ _ _ _ _ _ . . ______.-_l.___.___
l Table 1 (1 of 1)
REPORT CATEGORY : E4TCH RELEASE SLNWiY ELEASE FOINT : ALL TYFE OF RELEASE : SATCH LIQUID AND GA$E003 ERIOD START TIME : 1488:00 m3 = 12:00AM MARCH 4 1985 7 PERIOD END TIME : 4343:*9 HRS = 11:5?PM JUNE 30,1985 '
l LIQUID RELEASES M ER OF RELEASES : 106 I TOTAL TIE FOR ALL RELEASES : 29680.0 MIWTES i MAXIM TIE FOR A RELEASE : 463.0 MI W TES AVERAGE TIE FOR A RELEASE : 280.0 .91 E TES i MINIM TIE FOR A RELEASE : 65.0 MINUTES AERAGE STREAM FLOW : 749168.4 OPM GASEOUS RELEASES ;
MER OF RELEASES : 30 4 TOTAL TIE Fm ALL RELEASES : 50694.0 MIETES MAXIM TIE FM A RELEASE : 8496.0 MI W TES i AVERAGE T!E FOR A RELEASE : 1689.8 MI W TEF MINIM TIE FOR A RELEASE : 41.0 MINUTEfi ,-
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Table Li (1 of 1)
A& TAT CATEGCRY : !EMIAf.NUAL SUMMATION OF ALL RELEA3E3 BY 00ARTER TYPE OF ACTIVITY : ALL AIREGiNE EFFL"ENTS REPORTING PERIOD : QUARTER e 1 AND QUARTER d 2
- UNIT :0UARTER1:ChRTER2:EST. TOTAL: [
- :H)URS :H)URS : ERROR % : !
TYPE LT EFFLUENT : : 1-2160 :2151-4344 : :
l A. FISSION AND ACTIVATION PRODUCTS [
. . r
- 1. TOTAL RELEASE : CURIES : 1.46E-02 : 1.29E 03 : 1.50E 01: t
. .. i
- 2. A'4 RAGE RELEASE RATE FOR PERIOD :UCI/SEC : 1.4:E-03 1.25E 02 : !
- 3. PERCENT OF APPLICABLE LIMIT % N/A : N/A :
e B. RADIO!0 DIES ,
i
- 1. TOTAL 10 DIE-131 : CURIES : 0.00E-01 5.95E-04 : 1.50E 01: !
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 0.00E-01 8 5.73E-05
- 3. PERCENT OF APPLICABLE LIMIT I I : N/A N/A :
1 1
C. PARTICIA.ATES
- 1. PARTIClLATES(HALF-LIVES)8 DAYS) CURIES :0.00E-01:7.85E-07:1.5E01:
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC : 0.00E-01 7.63E-08 : l i
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A : i
- 4. GROSS ALPHA RADI0 ACTIVITY :CLRIES : 0.00E-01 : 3.5CE-06 :
l D. TRITitM
- 1. TOTAL RELEASE :CtRIES : 0.00E-01 0.00E-01 : 1.50E 01: e I
- 2. AVERAGE RELEASE RATE FOR PERIOD :UC!/SEC : 0.00E-01 0.00E-01 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A l
1-l
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Table IB (1 of 4)
REPORT CATEGm Y : SEMIANNUAL AIRBORNE CCNTIMJCU3 ELEVATED AND CRCMD
- LEVEL RELEASES. TOTALS FOR EAdi NLCLICE RELEMED.
TYPE OF ACTIVITY : FISSION GASES. !0 DINE 3, AND PARTICLLATES REPORTING PERIOD : QUARTER 8 1 AND OUARTER # 2
- ELEVATED RELEASES : F<)UND RELEASES :
- LMIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- :HOLRS :HOLRS :HOLRS :HOUES :
MJCLIIE : : 1-2160 :2161-4344 : 1-2160 82161-4344 :
FISSION CASES KR-85M : CURIES :0.00E-01:0.00E-01I0.00E-01:0.00E-01:
G-85 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-87 : CURIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-88 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
IE-131M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.0 E-01 :
IE-1331 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.26E 00 :
IE-133 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.40E 02 :
IE-135M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01
- IE-135 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.24E 00 :
IE-138 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
AR-41 : CIRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
0TER : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.52E 02 :
10DI!ES I-130 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
I-131 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-013 4.37E-04 :
I-132 : CLRIES : 0.0 E -01 : 0.00E-01 0.00E-01 : 0.00E-01 :
1-133 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.16E-06 :
1-134 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
1-135 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-41 : 0.00E-01 :
OTER : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TOTIL FOR PERIOD : C! RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.43E-04 :
e w
Table IB (2 of 4)
REPmi CATE0my : $EMIANNbAL AIRBCM E CONTINU0US ELEVATED AND GROUND
- LEWL RELEASES. TOTALS FM EACH NUCLICE RELEASED.
TYPE (F ACTIVITY : FISSICN GASES, IC0iNES. AND PARTICULATES REPORI!NG PERIOD : QUARTER 81 AND QUARTER 8 2
- ELEVATEDRELEAhS : GROUND RELEASES :
- (NIT :7J^RTER 1 :?fRTER 2 :?f.R5R 1 :0'fRTER 2 *:
- : * * *e ***
u ri ne . :HOLos..siin e .H0.tRS c .439 : g.2 30 :: g:.4744 :
PARTICULATES C-14 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
NA-24 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
P-32 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.0Cf-01 i CR-51 : (1 RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
796-54 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
796-56 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
FE-55 : CtRIES : 0.00E-01 : 0.00E-01 1 0.0CE-01 0.00E-01 :
FE-59 : CtRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
C0-56 : CLRIES 0.00E-01 0.00E-01 : 0.00E-01 2.76E-07 :
C0-60 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
NI-63 : CURIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
NI-65 : ClRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 !
C1)-64 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :
ZM-65 : CIRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
BR-83 : CLRIES 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
BR-04 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
IR-85 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
RB-96 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
RB-88 : CLRIES : 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
RB-09 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
SR-89 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :
SR-91 : CtRIES : 0.00E-01 0.00E-01 0.00E-01 : 0.0E-01 :
SR-92 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 Y-91M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-92 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-93 : C: RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ZR *5 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ZR-97 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Table IB (3 of 4)
. DEPORT CATE000.Y : SE"If.T!JAL n!EETfE C0*lTINUQUS ELE"ATED TAD EL*c
- LEVEL eELEASES. TOTALS FCP. EACH NUCL!IE *ELEASED.
TYPE 7 ACTIVITY : FISSION GASES, 10 DINES. FAD PADT!CULATES cEPORT!!4 PERIOD : QUARTER 8 1 AND GUARTER 8 2
- ELEVATED RELEASES : CROUND RELEASES :
UNIT QUARTER 1 : QUARTER 2 : QUARTER 1 CUARTER 2 :
. : : HOURS : HOURS :HOLRS : HOURS :
NUCLIDE : : 1-2160 82161-4344 : 1-2160 :2161-4344 :
PARTIClt.ATES CONTINlED 70-95 : CURIES : 0.00E-01 : 0.00E-01 500E-01:0.00E01:
MD-99 : CtRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TC-99M ClRIES : 0.00E-01 0.00E-01 : 0.0CE-01 : 0.00E-01 :
TC-101 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
AU-103 : CtRIES : 0.00E-01 : 0.00E-01 0.0CE-01 : 0.00E-01 :
RU-105 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : i RJ-1% : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
AG-110M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-125M : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : ;
TE-129 : CIRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.03E-01 :
TE-131M : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
TE-131 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-132 : C1 RIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
CS-134 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
CS-136 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CS-137 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.39E-07 :
CS-138 : CLRIES : 0.00E-01 : 0.00E-01 10.00E-01 : 0.00E-01 : '
BA-139 : CLRIES : 0.00E-01 10.00E-01 : 0.00E-01 0.00E-01 BA-180 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
84-141 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.0CE-01 :
84-142 : CLEIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
LA-140 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
LA-142 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-141 : C! RIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-143 01 RIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-144 : CIRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : !
PR-143 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
PR-144 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
P f
{
i Table IB (4 of 4) .
REPORT CATEGORY : SEMIANNUAL AIRBOR E CGNTINUOUS ELEVATED AND GR M D
- LE'4L RELEASES. TOTALS FOR EACH NUCLIIE RELEASED. l TYPE OF ACTIVITY : FISSION GASES. 10 DINES. AND PARTICULATES 1EPORTING PERIOD : QUARTER 61 AND QUARTER # 2 r
- ELEVATED RELEASES : GROUND RELEASES : -
LMIT : QUARTER 1 : QUARTER 2 :CUARTER 1 : QUARTER 2 : l
- H0lRS : HOURS : HOURS :H0lRS : ;
NUCLIDE : : 1-2160 :2161-4344 1-2160 :2161-4344 : ,
l PARTIClLATES CCNTIED [
2-147 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : i W-187 : ClRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
IF-239 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : l SR-90 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : ;
G AUM : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.58E-06 : L OTER : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : l t
TOTAL FOR PERIOD - CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 4.29E-06 :
t
)
[
t r
r k
e e
9
- - , . - - e, e +
Table 1C (1 of 4)
PEPORT CATE0mY : SEM!f.9tJAL A!RSTNE PATCH EL.'ATED AND CPOUND
- LEVEL RELEASES. TCTftS F T EACH P!JCL!DE PSH f. SED.
TYFE & ACTIV!!Y : F!S$!0N GASES 10 DIES. f!!D Pt.RT!C!)LATES REPOPT!NGf!R!0D : CUARTER 8 1 AND CunRTER S 2
- ELEVATED RELEASES : GR0tND RELEASES : ,
- UNIT QUARTER 1 : QUARTER 2 : QUARTER 1 1.1UARTER 2
- :H0 RS : HOWS : HOURS HOURS :
MJCLIDE : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
FISSION GASES KR-95M : CW!ES : 0.00E-01 : 0.00E-01 : 4.89E-05 : 1.3"E-01 :
rJt-85 : C2 !ES : 0.00E-01 : 0.00E-01 : 0.00E-01 9.17E-04 :
KR-97 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
KR-SS : CLR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.51E-03 :
IE-131M : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 1.17E 00 :
IE-133I : CLRIES : 0.00E-01 1 0.00E-01 8 3.79E-04 4.96E 00 :
IE-133 : CtRIES : 0.00E-01 : 0.00E-01 1.19E-02 3 3.24E 02 :
IE-135M : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
IE-135 : CtRIES : 0.00E-01 : 0.00E-01 : 2.36E-03 5.01E 00 :
IE-138 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
AR-41 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
OTER : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
TOTAL FOR PERIOD : C1 RIES : 0.00E-01 : 0.00E-01 1.46E-02 3.35E*02 :
IODIES I-130 : CURIES : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :
I-131 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 1.50E-04 :
I-132 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :
I-133 : . CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 5.35E-05 1-134 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
1-135 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
OTER : CURIES 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :
TOTAL FOR PERIOD : C1 RIES 0.00E-01 : 0.00E-01 0.00E-01 2.11E-04 :
P
Table 1C (2 of 4) cI?Ooi CATE0 CRY : SEMIA!NUAL A!oo0RNE BATCH ELEVATED 20 0.o0tND
- teyo_ petcAeEe vnm e ere ceu uce ene ca eneen TYFE Oc ACTIV!!Y : c;gsges cesgg, geeig g, 339 ,ongy cttargs E 0*TI.T FE0!00 ^
- 00..RTEC i 1 AND 00nRTER t 2
^
- " eVATED
_ o.o EASES : 500L*..D
. oELE..SES :
- tNIT :0UnRTER ! l00nRTER 2 QUARTER 1 :0UARTER 2 5
- :HOLRS :HOLJRS :H0lRS HCARS :
10CLIlE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
PARTIC1LATES
. C-14 : CIRIES : 0.00E-01 : 0.00E-01 : 0.0 E-01 : 0.00E-01 :
NA-21 : CL*.IES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
P-32 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CR-51 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
191-5 4 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
.W-56 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
FE-55 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
FE-59 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CD ',9 : CtRIES : 0.00E-C1 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CD-60 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
N!-63 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NI-65 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CU-64 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 ZN-65 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
BR-83 : CURIES 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
BR 94 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.0M-01 :
BR-05 : CtRIES : 0.00E-01 : 0.00E-01 : 0.0CE-01 : 0.00E-01 :
RB-86 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RB-88 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 2.22E-04 :
R9-89 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR 5 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR-91 : CLRIES : 0.00E-01 : 0.0LE-01 : 0.<0E-01 : 0.0T-01 :
SF '2 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-91M : CURIES : 0.00E-01 : 0.^CE-01 : 0.0CE-01 : 0.00E-01 :
Y-92 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-93 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
IR-95 : C! RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ZR-?7 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
e
+r.
Table 1C (3 of 4) i REPORT CATE00RY : SEMIAMAJAL AIRfKRT BATCH ELEVATED AND GROUND
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GA3ES. ICDINES. AND PARTICLiATES REPORTING FERIOD : QUARTER 8 1 AND QLARTER # 2
- ELEVATED RELEASES : CEtND RELEASES :
- LNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 JJARTER 2 :
- :HOlR$ : HOURS : HOURS :H0lRS :
MJCLIDE : : 1-2160 :2161-4344 1-2160 82161-4344 :
PARTIC1LATES CONTIMJED fe-95 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
MD-99 : CtRIES : 0.00E-01 : 0.00E-013 0.00E-01 : 0.00E-01 :
TC-99M : CURIES : 0.0CE-01 : 0.00E-01 : 0.00E-01 0.0E-01 :
TC-101 : CtRIES : 0.00E-01 : 0.0CE-01 : 0.00E-01 : 0.00E-01 :
RU-103 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-105 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-106 : CLRIES : 0.00E-01 : 0.00E-01 1 0.00E-01 1 0.00E-01 :
AG-!!0M : CLRIES : 0.00E-01 : 0.0(E-01 : 0.00E-01 : 0.00E-01 :
TE-125M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-129 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
TE-131M : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
TE-131 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
TE-132 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 6.99E-08 :
CS-134 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CS-136 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CS-:37 : CLRIES : 0.00E-0! : 0.00E-01 : 0.00E-0: : 0.00E-01 :
CS-139 : CLE!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.0M-01 :
94-139 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
94-140 CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
BA-141 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
84-142 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
LA-140 : CtRIES 0.00E-01 0.00E-01 0.00E-01 10.00E-01 :
LA-142 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE :41 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
E-143 : CIRIES : 0.00E-01 : 0.00E-41 0.00E-01 : 0.00E-01 :
CE-144 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
PR-143 : CLRIES : 0.00E-41 : 0.00E-01 0.00E-01 : 0.00E-01 :
PR-144 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Table 1C (4 of 4)
REPORTCATEGORY : SEMIAftijAL AIRBORE BATCH ELEVATED AND GR0Ule
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GASES.100!ES. AND PARTICULATES REPORTING PERIOD : QUARTER S 1 AND QUARTER I 2
- ELEVATED RELEASES : GROLND RELEASES :
LMIT QUARTER 1 QUARTER 2 : QUARTER 1 QUARTER 2 :
- :H0lRS :H0lRS HOURS : HOURS MJCLIDE : : 1-2160 82161-4344 1-2160 :2161-4344 :
PARTIC1LATES CONTIRED 16-147 : CURIES 0.00E-01 : 0.00E-01 0.0 E-01 0.00E-01 :
Id-187 : CtRIES : 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
W-239 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
SR-90 : CLRIES : 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
G ALPH4 : CURIES 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :
OTER : CLRIES : 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
TOTAL FOR PERIOD : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 2.22E-04 r
i E
s t
b L
I L
Table 2A (1 of 1)
REPORT CATEGORY SEMIANAL SIMeT!0N OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY : ALL LIQUID EFFLUENTS REPORTING PERIOD : QUARTER 81 E QUARTER e 2
- (MIT : QUARTER 1 QUARTER 2 IEST. TOTAL:
- HOURS : HOURS
- ERROR % :
TYPE OF EFFLLENT : 1 1-2160 :2161-4344 : :
A. FISS!(W M ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING : : :
TRITM. GASES. ALPHA) :CLRIES : 0.00E-01 8 4.19E-02 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : :
, DLRING PERIOD :UCInt. 0.00E-01 1 5.87E-10
- 3. PERCENT OF APPLICABLE LIMIT 1 : N/A : N/A
- 8. TRITitM
- 1. TOTAL IELEASE :CLRIES : 0.00E-01 4.59E 00 1.50E 01:
- 2. AWERAGE DILUTED CONCENTRATION : :
- DLRING PERIOD IUC!nt. 0.00E-01 1 6.4 X-08 :
- 3. PERCENT (F APPLICARE LIMIT 1 : N/A N/A C. DISSOL\ED M ENTMIED GASES
- 1. TOTAL FELEASE ICtRIES 2.36E-05 8.60E-01 1.50E 01:
- 2. AVERAGE DILUTED CONCENTMTION : : : :
DURING PERIOD IUC!nt. I 1.82E-12 1.21E-08
- 3. PERCENT OF APPLICABLE LIMIT 1 : N/A N/A D. GROSS ALPHA RADI0 ACTIVITY
- 1. TOTAL RELEASE CtRIES : 1.54E-06 6.85E-06 1.50E 01:
E. MSTE VOL lELEASED(PIE-DILilT19) IGAL 2.30E 05 : 7.57E 06 8 2.00E 00:
F. YOUAE OF DILUTIM WTER INED IGAL 3.42E 09 1.8tE 10 a 2.00E 00:
Table 2B (1 of 4)
REPORT CATEGORY SEM!AfMIAL LIQUID CCNTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLICE RELEASED.
TYPE CF ACT!V!TY ALL RADIONUCLIDES REPORTING PERIOD AARTER 81 MD MTER I 2
- CONTIMJOUS RELEASES BATCH RELEASES I I UNIT 20UARTER I 80UARTER 2 IQUARTER 1 ICUARTER 2 :
- HOURS tHOURS IHOURS IHOURS t 70CLICE. t t 1-2160 I2161-4344 1-2160 12161-4344 ALL NUCLIDES H-3 CURIES 0.00E-01 2.18E-03 3 0.00E-01 1 4.59E 00 :
C-14 : CLRIES I 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 :
NA-24 : CtRIES 0.00E-01 2.68E-05 I 0.00E-01 2.60E-05 :
P-32 : CtRIES 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR-51 : CURIES : 0.00E-01 0.00E-01 I 0.00E-01 14.29E-03 196-54 : CLRIES t 0.00E-01 : 0.00E-01 1 0.00E-01 2 2.25E-04 8 4
791-56 i CUR!ES 0.00E-01 I 0.00E-01 0.00E-01 1 0.00E-01 i FE-55 : C'JRIES
- 0.00E-01 0.00E-01 t 0.00E-01 0.00E-01 :
FE-59 : CtRIES t 0.00E-0! t 0.00E-01 1 0.00E-01 2 4.19E-01 :
CO ".S CUR!ES t 0.00E-01 2 0.00E-01 2 0.00E-01 1.18E-02:
C0-60 CLRIES 0.00E-012 0.0CE-01 : 0.00E-01 13.46E-01 N!-63 : CLRIES 0.00E-01 0.00E-01 0.00E-01 1 0.00E-01 N!-65 i CUR!ES 0.00E-01 : 0.00E-01 ! 0.00E-01 0.00E-01 :
CU-64 : CLRIES 0.00E-01 : 0.00E-012 0.00E-01 4.06E-04 :
IN-65 i CtRIES t 0.00E-01 2 0.00E-01 0.00E-01 0.C @ 01 IN-69 t CLR!ES t 0.00E-01 2 0.00E-01 0.00E-01 0.00E-01 I BR-83 i CURIES 0.00E-01 0.00E-01 0.00E-01 10.00E-01 :
BR-84 : CtRIES 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
IR-85 : CtRIES 0.00E-01 0.00E-01 0.00E-01 : C.00E-01 RB-86 : ClRIES 0.00E-01 10.00E-01 I 0.00E-01 0.00E-01 :
RB-88 i CURIES 0.00E-01 0.00E-01 I 0.00E-01 1 2.11E-04 I RB-89 CURIES 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 SR-89 :I , CURIES : 0.00E-01 0.00E-01 0.00E-01 8 0.00E-01 SR-91 I CURgr.S I 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
SR-92 I CURI O I 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 Y-90 t QRIES : 0.00E-01 0.00E-01 I 0.00E-018 0.00E-Cl !
Y-91M t CtRIES 0.00E-01 : 0.00E-01 0.00E-012 0.00E-01 Y-91 I CtRIES t 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01
- e
Table 2B (2 of 4)
REPORTCATEGORY : SEMIAMAJAL LIQUID CONTIMJ0US AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
TYFE OF ACTIVITY : ALL RADI(NUCLIDES REK6TINO PERIOD : QUARTER 41 AND QUARTER 8 2
- CONTIMJOUS RELEASES : BATCH RELEASES :
- UNIT : QUARTER 1 :0UARTER 2 : QUARTER 1 : QUARTER 2 :
- :H0tRS : HOURS HOURS :H0tRS :
NUCLIM : : 1-2160 :2!61-4344 : 1-2160 :2161-4344 :
ALL MJCLIDES CCNTIMED Y-92 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-93 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
IR-95 : CLETES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.85E-04 :
ZR-97 : CLR!aS 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.90E-05 16-95 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.99E-04 :
MD-99 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 1.21E-04 :
TC-99M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.97E-04 :
TC-101 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-103 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-41 :
RU-105 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
RU-106 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
-AG-110M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
TE-125Pt : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-127M : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-127 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-!2*P. : CtR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-129 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-131M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-131 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-132 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
!-130 : CURIES : 0.00E-01 : 4.00E-01 : 0.00E-01 : 0.00E-01 :
!-131 : C! RIES : 0.00E-01 : 1.72E-05 : 0.00E-01 : 4.54E-03 :
I-132 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-133 : CtRIES : 0.00E-01 2.27E-05 : 0.00E-013 5.25E-04 1-134 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :
I-135 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CS-134 : CLRIES : 0.00E-01 0.00E-01 0.00E-01 0.00E-01 :
CS-136 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 2.84E-05 :
Table 2B (3 of 4)
REPORT CATEGORY : SEMIANMJAL LIQUID CONTINUOUS AND BATCH FELEASES
- TOTALS FOR EACH NUCLICE RELEA5ED.
TYPE OF ACTIVITY : ALL RADIONUCLIES REPORTING FERIOD ' : O'#5TER t 1 AND OUARTER 4 2 ICONTINUOUSRELEASES: BATCH RELEASES :
- UNIT : QUARTER 1 : QUARTER 2 :QUf4TER 1 : QUARTER 2 :
- H0lRS : HOURS : HOURS : HOURS :
MJCLIE : : 1-2160 :2161-4344 1-2160 82161-4344 :
l ALL MJCLIDES CONTIMED '
CS-137 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.91E-04 :
CS-138 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
B4-139 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
84-140 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.0!E-06 : !
! BA-141 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.0E-01 : {
94-142 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
LA-190 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.03E-03 :
l LA-142 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-141 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
-143 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-144 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.79E-03 :
PR-143 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
PR-144 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
M)-147 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :
14-187 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 7.83E-03 :
, IF-239 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i KR-S3M : CURIES : 0.00E-01 : 0.0%-01 : 0.00E-01 : 0.00E-01 :
KR-95M : C! RIES : 0.00E-01 : 0.00E-01 0.00E-01 : 1.41E-04 :
KR-85 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-97 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-SS : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.0?E-05 :
KR-89 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-90 : CLRIES : 0.00E-0! : 0.00E-01 : 0.00E-01 : 0.00E-01 :
IE-131M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.56E-04 :
IE-133M : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.0!E-02 : ,
IE-133 : CLRIES : 0.00E-01 : 1.30E-04 : 2.36E-05 : 3.2"E-01 :
IE-135M : CURIES : 0.00E-01 : 0.00E-01 : 0.0E-01 : 0.00E-01 :
IE-135 : CUR!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.43E-02 :
_ I
Table 2B (4 of 4) 4 REPORT CATEGORY : SEMIAfMJAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS F M EACH NUCLIDE RELEASED.
TYFE 0F ACTIVITY : ALL RADIONUCLIDES REPORTING FERIOD : OVARTER 0 1 AND QUARTER 4 2
- CONTINUOUS RELEASES : BATCH RELEASES
- L?!!! :00CTER 1 : QUARTER 2 :00ARTER 1 :00ARTER 2 :
- :HCURS : HOURS : HOURS :HCtRS :
RICLIDE. : : 1-2160 :2161-4344 : 1-2160 :2161-4341 :
lLL NUCli]ES CNTIEED XE-137 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
IE-138 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
AR-41 : CURIES : 0.00E-01 : 0.00E-012 0.00E-01 : 0.00E-01 :
SR-90 : CURIES : 0.00E-01 : 0.00E 't 0.00E-01 : 0.00E-01 :
G ALPHA : CURIES : 3.00E-01 : 0.00E-01 : 1.54E-06 6.85E-06 :
OTER : C1 RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TOTAL FOR PERIOD ~ ! C1 RIES : 0.00E-01 2.37E-03 2.51E-05 : 5.49E 00 I
a 4 !
h i
b s
i 0
i 7
i h
I
TABLE 3 (1 of 1)
- REGULATORY CUIDE 1.21 REPORT ***
SOLID WASTE SHIPPED OrJ3ITE FOR DISPOSAL
- DURINC PERIOD FROM 1/1/85 - 6/30/85 WASTE TYPE CUBIC METERS CURIES 7. ERROR (CI)
EB-S-CM Bottoms 5.15 .379 +/- 25%
SR-D-NA Blowdown & RCS Bead Resins 5.15 .282 +/- 25%
- ESTIMATES OF MAJOR NUCLIDES BY WASTE TYPE **
WASTE TYPE NUCLIDE ABUNDANCE CURIES Evaporator Bottoms H-3 0.05% 2.0E-04 Solidified with co-58 8.8% 3.34E-02 Cement Co-60 .4% 1.5E-03 I-131 86.5% 3.28E-01 Cs-137 2.5% 9.5E-03 Dewatered Spent Steam H-3 7.5% 2.12E-02 Cenerator Blowdown and Cr-51 5.6% 1.58E-02 RCS Bead Resin Mn-54 1.5% 4.2E-03 Co-58 14.7% 4.17E-02 Co-60 0.8% 2.5E-03 I-131 66.3% 1.87E-01
- SOLID WASTE DISPOSITION
SUMMARY
NUMBER OF TYPE OF TYPE OF MODE OF CLASS SHIPMENTS SHIPMENT CONTAINER TRANSPORATION DESTINATION :
A 1 LSA Strong Tight Truck Richland B None * * *
- C None * * * *
- IRRIATED COMPONENTS / FUEL SHIPMENTS ***
None
- Not Applicable
1 of 6 ATTACHIM 1 TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
A. Batch Waste P P Release Each Batch Each Batch' Principal Gamma 5x10 7 Tanks b ,f,g,h,i Emitters c
- 1. Boric Acid I-131 1x10 6 Condensate P M Dissolved and 1x10 5 Entrained Gases
- 2. Waste One Batch /M (Gamma Emitters)
Condensate P M d
H-3 1x10 5 Each Batch Composite
- 3. Laundry Gross Alpha 1x10 7 Waste
- 4. Turbine P Q Sr-89, Sr-90 5x10 8 Building d Each Batch Composite Industrial Waste Fe-55 1x10 6 Sumps *
- 5. Dry Cooling f Tower Sumps
- 1 and #2*
- 6. Regenerative Waste
- 7. Filter Flush
- 8. Waste ,
'Wh;n release from this source is batch in nature.
WATERFORD - UNIT 3 3/4 11-2
2 of 6 AITAOR M 1 r : -
TABLE 4.11-1 (Continued)
.~.
LOWER LlHII MINIidM OF OETECTIOM LIQUID RELEASE SMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FitEQUENCY FREQUENCY MALYSIS (pci/mL)
- 8. Continuous W W Principal Gasana 5x10 7 Releases e.f I
. Grab Sample Emitters" L Turbine
I-$1 1x10
- Building -
. Industrial h I Waste Sumps **. .
M M Dissolved and 1x10 5
- 2. Dry Cooling Grab Sample Entrained Gases . I Tower i (Gamma Emitters) sa,p plen
~
- 3. Dry Cooling W . M H-3 MM Tower i Grab sample composite d g
- Sep e .
Grost Alpha 1x10 7
- 4. Circulating - W Q 3 " 08' 3 "
. Water ,
, Grab Sample Compositad Ofscharge- - Fe-55 1x10 8
. .. Steam Gene-rator Slow- .
. down HX >
- 5. Auxiliary Camponent i Cooling i Water Pumps i
- when release free this source is continuous in nature. ,
WATERFORD - UNIT 3 3/4 11-3 ANENOMENT NO. 1
3 of 6 !,
ATTACHMENT 1 ,
TABt.E 4.11-1 (Continued)
I NIMIMUM LOWER LIMIT' LIQUID RELEASE $ANFLING r,- OF DETECTION ANALYSIS TYPE OF ACTIVITY TTFE (LI,D)a FREQUENCY FREQUENCY ANALYSIS (uCi/aL)
B. Contimoons W W Principal camma 5x10~7 Releases e,f Continuoud Composite Emitters" 6 Steam Generator I-131 1x10 '
~
Blowdown -
l Disch1rge $1* i l
l M M Dissolved and 1x10-5 Crab Sample Entrained Gases '
(Gamma Emitters)
E N H-3 lx10-5 Continoons Composite d l
1 Cross Alpha tzl0 l [
p W Q Sr-89. Sr-90 Continuousk composite 3x10' i
Fe-35 lx10-6 b
l >
I t
I i .
. i I
j i
4 i
NATERFORD - UNIT 3 3/4 11-3e AMENDMENT NO. 1 !
4 of 6 ATTAQt ETr 1 TABLE 4.11-1 (Continued)
TABLE NOTATION a
The LLD is defined, for purposes of these specifications, 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 only ;
5% probability of falsely concluding that a blank observation represents a '
"real" signal.
I For a particular measurement system, which may include radiochemical separation:
LLD =
E V 2.22 x 106 Y exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above' as microcuries per unit mass or volume, shis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as countc per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measureneiit system and not as an a posteriori (after the fact) limit for a particular measurement.
b A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.
WATERFORD - UNIT 3 3/4 11-4
t 5 of 6 AITACHMENT 1 TABLE 4.11-1 (Continued)
TABLE NOTATIONS c
The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, ;
Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean j that only these nuclides are to be considered. Other gamma peaks that are !
identifiable, together with those of the above nuclides, shall also be analyzed I and reported in the Semiannual Radioactive Effluent Release Report pursuant to l Specification 6.9.1.8.
d A composite sample is one in which the quantity of liquid sampled is proportional !
to the quantity of liquid waste discharged and in which the method of sampling '
employed results in a specimen that is representative of the liquids released. i
'A continuous release is the discharge of liquid wastes of a nondiscrete l volume, e.g., from a volume of a system that has an input flow during the !
continuous release.
I Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent -
release.
U lf the contents of the filter flush tank or the regenerative waste tank contain detectable radioactivity, no discharges from these tanks shall be made !
to the UNRESTRICTED AREA and the contents of these tanks shall be directed to ,
the liquid radwaste treatment system. t h
Turbine Building Industrial Waste Sump (TBIWS)
The TBIWS shall be required to be sampled and analyzed in accordance with this table if any of the following conditions exist:
(1) Primary to secondary leakage is occurring; or, (2) Activity is present in the secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, (3) Activity was present in the TBIWS during the previous 4 weeks.
If none of the above situations exists, then the sampling and analysis of this :
stream need not be performed. ,
I Sampling and analysis of the dry cooling tower sumps and the auxiliary component cooling water pump discharge will be required only when detectable activity exists in the CCW.
Sampling and analysis of the circulating water discharge-steam generator blowdown heat exchanger discharge (CWD-SGB) will be required only when detectable activity exists in the secondary system.
- WATERFORD - UNIT 3 3/4 11-5
, --.r, .. -- - - . . - . . - . , ,
6 of 6 i K1TACHMENr 1 I
Table 4.11-1 (continued)
TABLE NOTATIONS i.
I 3 ...
Sampling and analysis of the stesa generator blowdown vill be required !
only when the blowdown is directed to the circulating water system or '
Baterford 3 waste pond. ' ' '
,, Steam generator blowdova to the Waterford 3 wasta pond will be limited to ,
situations requiring secondary chemis,try control where the Circulating ,
veter system is not available or the secondary chemistry is outside the ,
requirements for.Carcelating Water System discharge. Blowdown to the i
)
wasta pend will be terminated spoo detection of sample a' ctivity greater than the LLD lispels of Table 4.21-1 Section B. - !
l ko be repres'entative of the quantities and concentration of radioactive materials in liquid effluents,' samples shall be collected continuously -
I in proportion to the rate of flow of the affluent stream.
I Steam generator blowdown discharge to the waste pond shall be limited to a period of six months with the circulating water system discha'rge'
~ ., path not available unless. radiation monitoring and automatic isolation i capabilities are added to the waste pond discharge path. !
J ;
I l
t !
' I a
I e i 1
I i
l
- c i
l i 1
- WATEgroap - UNIT 3 3/4 11-Se AMFNf9FMT NO. 1
.,, - - - , - - - ,. - , , , - - - ---,---w.--,w.v,-,-ww--..-,,,w.,-e -..v -y--y----... - - - --.~ -w, .*,-w--e,,-.,,--.w.w-w-+---w - -+ w, .w ,..,y -
-r -
, TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM o MINIMUM LOWER LIMIT OF 5 SAMPLING ANALYSIS TYPE OF DETECTION (LLD)*
i GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/mL) e P P 5
A. Waste Gas Holdup Each Tank Each Tank Principal Gamma Emitters b 1x10 4 Tanks Grab Sample P P c c B. Containment PURGE Each PURGE Each PURGE Principal Gamma Emitters b 1x10 4 (Plant Stack) Grab Sample M H-3 1x10 8 C.1 Plant Stack Mc .d,i Principal N ble Gas Gamma 1x10 4 b
Grab Sample M Emitters H-3 1x10 6 R
C.2 Fuel Handling Md Principal Noble b
Gas Gamma 1x10 4 Building Ven- Grab Sample M Emitters O
tilation H-3 1x10 6 (Normal)
Exhaust D.1 All Release Types Continuousf ,h,j gg I-131 1x10 12 "
as listed in Charcoal B., C.1, and Sample I-133 1x10 20 C.2 above D.2 Main Condenser Continuousf ,h,j gg 1x10 11 PrincipafParticulateGamma Evacuation and Particulate Emitters Turbine Gland Sample Sealing System Continuous #'h'd M Gross Alpha 1x10 12 Composite Particulate Sample Continuous #'A'd Q Sr-89, Sr-90 1x10 11 Composite Particulate
- Sample Continuousf ,h,j Noble Gas Noble Gases 1x10 8 Monitor Gross Beta or Gamma l
)
i' 2 of 3 ATTA(RDTI 2 -
TABLE 4.11-2 (Continued) ,
TABLE NOTATION a
The LLO is defined, for purposes of these specifications, as the smallest i concentration of radioactive material in a sample that will yield a net count, ,
' above system backgrour.d, that will be detected with 95% probability with only [
5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical !
separation: l 4.66s I b
LLD =
E V 2.22 x 105 Y exp (-Aat) i 1 Where: ,
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s g is the standard deviation of the background counting rate or of the c5unting rate of a blank sample as appropriate, as counts per minute, ,
E is the counting efficiency, as counts per disintegration, i V is the sample size in units of mass or volume, l 2.22 x 10s is the number of disintegrations per minute per microcurie, i Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and ,
at for plant effluents is the elapsed tine between the midpoint of sample '
collection and the time of counting.
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a poste~iori (after the fact) limit for a particular measurement.
e WATERFORD - UNIT 3 3/4 11-11 .
3 of 3 4
AITACHtENr 2 i'
. TABLE 4.11-2 (Continued)
! TABLE NOTATIONS
! The principal gamma emitters for which the LLD specification applies include ;
j the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and >
- Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, i 1-131, I-133, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate !
l releases. This list does not mean that only these nuclides are to be l considered. Other gamma peaks that are identifiable, together with those of l the above nuclides, shall also be analyzed and reported in the Semiannual l Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.
C I
Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, 3 or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a i l 1-hour period. Analysis for principle gamma emitters as defined in (b) I j above shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sampling, f' dTritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the f
-refueling canal is flooded.
' Tritium grab samples shall be taken at least once per 7 days from the [
ventilation exhaust from the spent fuel pool area, whenever spent fuel is in i j the spent feel pool. [
t
! IThe ratio of the sample flow rate to the sampled stream flow rate shall be l i
j known for the time period covered by each dose or dose rate calculation made j in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3. [
r
! 95amples shall be changed at least once per 7 days and analyses shall be i completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. ,
i Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least !
i i 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed !
i within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are !
j analyzed, the corresponding LLDs may be increased by a factor of 10. This ;
i requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 l
concentration in the primary coolant has not increased more than a factor of i
3; and (2) the noble gas monitor shows that effluent activity has not i increased more than a factor of 3. :
h l If no primary to secondary leakage exists, then only the gross beta or gamma [
noble gases analysis need be performed for the main condenser evacuation and j turbine gland sealing system. If a primary to secondary 4eak exists and the ;
release from the main condenser evacuation and turbine gland sealing system !
- has not been released via the plant stack, then the sampling and analysis l must be performed, f;
! Note (c) above is not applicable for the plant stack unless the noble gas j monitor shows that effluent activity has increased by a facto; ef 3. j i.
3 Fuel Handling Building sampling is required whenever irradiated fuel is in i
- the storage pool. ;
i
, WATERFORD - UNIT 3 3/4 11-12 l 2 i
1 ATTACHMENT 3 PROCESS CONTROL PROGRAM, RW-1-210, REVISION 1 [
I LOUISIANA i
POWER & LIGHT l E sys M POM VOLtjME 20 . . .
C
. RW-1-210 POM SECTION 1 REVISION 1
{
THIS IS TO CERTIFY THAT THIS PROCEDURE IS THE LATEST REVISION IN EFFECT AS JUNE 30, 1985. .
i ADMINISTRITIVE PROCEDURE
PORC Meeting No.
Reviewed '
dw PORC Chairman
/ C"30 84~
DATE Approved hM / [( [
PlantManaggp(clear /DATE r
Effective Date UNT-1-002 Revision 9 22 Attachment 6.3 (1 of 4) i
RE7Ir4 COVE 3,Sc._ .
RE7Ird CT: RW-1-210 - Process Control Program (Rev.1)
PCRC R. N J The PCEC has reviewed this ites and deternised that a safety evaluation was perfor=ed j (as applicable), that an unreviewed safety question does not exist (as applicable),
that a change to the Technical specifications is not required, and that nuclear safa:7 is/vas not adversely affected.
~
0EDE1 REC teENDED 07 PORC IEMBE1 FORC MI2fBE1 FOR AFFROVAL DATI 11 TIE 7 SIGNATURK TIS l NO Maintenance Superintendent ,
[(/ /
h I'Y 'N Operations Superintendent / f e/g Radiation Protection. ./ //
~
Superintendent- ,
/ 5%;/f 31 sat Quality Manager bg j~- '
/J s'r
~
C O 2?*** /da,1 #
9fd -
Assistant 71 sat "/ '/
Manseer
- kN '
3-30-3[ >
i PCRC Meeting No.#4"-AM '
Itan No /D Daset #-vP# - W This iten is reco M ed for approval? TES O no l This ites requiras s1C/NBC review prior to implementation 2 O Tzs -- @ NO If yes, ensure documentation supporting review is attached.
! This ites requires QA revia 9 prior to PM-N approval? O Trs E x0 l
l
- CA RZ7IEW i Rev1=ved by A)/ + nArE a/4 i i
Corporata QA Manager
- Pt.ATJ MNACE?-vtTCt. EAR AF?ROVAL (REFER TO 5.4.12.1) !
Comments:
I l
l
! I Approved by N/8 DATE M/A- j i Plant Manger-Nuclear ,
UNT-1-004, Revision 6 18 l
i
WATERFORD 3 SES
- PLANT OPERATING MANUAL Check Block Below CHANGE / REVISION /D TION REQUEST PO f l[lPORC-S/C Procedure No. [/O- /- 2/d Title ddt03 b// A)f?i'/(M Effective Date (if different from approval date)
Complete A, B, and C A. Change No. NA l[lPermanent l[lDeviation Expiration Date B. Revision No. / l C. Deletion l[ LYES 1 NO DESCRIPTION OF CHANGE OR REVISION W $ $1l00AbVO k /UkY$l l}'/8Y2N bC'Y11 to i y ACl$1/7%D p
REASON FOR CHANGE, REVISION, OR DELETION bb9 0lDh W //G$ #11fl0 AA) #d AD/lbO?bl/
h JYY11 fN N8h _)td4 C d h /Uthl$1/MA D
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i REQUIRED SIGRTURES ORIGINATOR /1MW)7[') . M N dan 4 v /# 5 SAFETY REVIEW Does this change, revision, or deletion:
- 1. Change the facility as described in the FSAR? YES No .
- 2. Change the procedures as described in the FSAR7 YES NO Y
- 3. Conduct tests / experiments not described in the FSA27 YES NO /
- 4. Require a change to the Technical Specifications? YES NO (
If the answer to any of the above is yes, complete and attach a .
10CFR50.59 S etyEvaluationf SATETY REVIEW /#f78) N.# /Mih dan 6 /35 n CnNICAt REvrEW yv/#2 Dm <>/<
GROUP aEAD REmm * (M=:n Dm f/1Rs TEMPORARY /PPROVAti (SRO) d '
_DATE TEMPORARY APPROVAL
- DATE
- Temporary approval must be followed by Plant Manager /APM-N - Nuclear approval within 14 days.
UNT-1-003 Revision 8 '3 Attachment 6.7 (1 of 1)
Administrativa Procsdura RW-1-210 Process Control Program Revision 1 1
i TABLE OF CONTENTS 1.0 PURPOSE i
s
2.0 REFERENCES
r 3.0 DEFINITIONS '
4.0 RESPONSIBILITIES 5.0 PROCEDURE !
5.1 Program Description ,
5.2 Solidification Process Parameters 5.3 Administrative Controls 5.4 Waste Characterization and Classification 5.5 Quality Assurance ,
i 6.0 ATTACHMENTS
- l LIST OF EFFECTIVE PAGES i Title Revision 0 l 1-11 Revision 0 t
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Administrativa Procedura RW-1-210
- Process Control Program Revision 1 j 1.0 PURPOSE I 1.1 The purpose of Waterford Steam Electric Station - Unit Number 3 (Waterford 3) Process Control Program (PCP) is to describe the l program which provides reasonable assurance of the complete solidifi-ation of various radioactive " wet wastes" including resin slurries i and evaporator bottoms are in accordance with applicable Department of Transportation (DGT), Nuclear Regulatory Commission (NRC), State d
and licensed burial facilities acceptance criteria for packaging and l shipment to an approved burial site. Compliance with these criteria j will be achieved through implementation of the PCP and.related Waterford 3 and vendor supplied procedures.
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2.0 REFERENCES
)
j 2.1 Waterford 3 Documents I
i 2.1.1 FSAR Chapter 16, Technical Specification 3/4 11.3 j
2.1.2 FSAR Chapter 16, Technical Specification 6.13.2 2.1.3 FSAR Chapter 11.4, Solid Waste Management System
- 2.1.4 FSAR Chapter 13.4, Review and Audit 2.1.5 FSAR Chapter 13.2, Training 2.1.6 FSAR Chapter 13.5, Plant Procedures i
i 2.1.7 Nuclear Operations Management Manual,Section VI, Chapter 5 2
Administrativa Procidura RW-1-210 Process control Program Revision 1 f
2.2 Vendor Controlled Documents 2.2.1 TR002, NUS Process Services Corporation, Topical Report on 10CFR61 Qualified Radioactive Waste Forms, May 1984 2.2.2 4313-01354-01P Cham-Nuclear Systems Inc., Topical Report on Mobile Cement Solidification System, Rev. 2 2.2.3 CNSI-WF-C-01-NP, 10CFR61, Waste Form certification-Cement, 4
. Chem-Nuclear System Inc., November 30, 1983 i
f 2.2.4 CNSI-DW-11118-01-P, Chem-Nuclear System, Inc., Dewatering Topical, Dacember 23, 1983 I
2.2.5 STD-R-05-005, Westinghouse Hittman Nuclear, Inc., Topical ,
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Report on Cement Solidified Wastes to Neet the Stability i r
Requirements of 10CFR61, Rev. 0 '
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2.2.6 STD-R-03-008, Westinghouse Hittman Nuclear, Inc., Topical- l Report for Hittman RADLOK High Integrity Containers, Rev. O j i
2.2.7 FI-013, Process Control Program for Dewstering Liner with NUS ,
PSC Internals, NUS Process Services Corp. I l
2.2.8 STD-P-05-003, Hittman Nuclear Development Corp. , Process ,
Control Program for Incontainer Solidification of 10 of 14 l ;
I Weight Percent Boric Acid, Rev. 1 ! ;
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2.2.9 STD-P-05-004, Hittman Nuclear Development Corp. , Process l
Control Program for Incontainer Solidification of Bead Resin, l Rev. 1 ,
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Administrativa ProcGdure RW-1-210 Process Control Program Revision 1 j 2.2.10 Hittman Nuclear Development Corp. , STD-P-03-005, Hittman Nuclear Development Corp. , Dewatering Hittman Radlock Containers with Flexible Underdrains to Less Than 1% Drainable Liquid, Rev. 2 2.2.11 STD-P-04-002, Dewatering Ion Exchange Resin and Activated Charcoal Filter Media to 0.5%
1 7
2.2.12 WMG 102-NP-A, Waste Management Group, RADMAN Tropical Report 2.3 Other Documents 2.3.1 10CFR61, Licensing Requirements for Land Disposal of Radio-l active Was:e 2.3.2 10CFR20.311, Transfer for disposal and manifests 2.3.3 10CFR71.91, Records 3.0 DEFINITIONS j MM 4.0 RESPONSIBILITIES j 4.1 Plant Manager-Nuclear 4.1.1 The Plant Manager-Nuclear has overall administrative control ,
responsibilities for the Process Control Program at Waterford-3.
He is responsible for ensuring the following:
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Administrativa Procsdura RW-1-210 Process Control Program Revision 1 4.1.1.1 The preparation, review and approval of the Process Control Program procedures pertaining to the process-ing and packaging, of radioactive materials, and for the operation and maintenance of radwaste systems; 4.1.1.2 That plant personnel adhere to the procedural require-ments of this progras; 4.1.1.3 That plant interdepartmental responsibilities affect-ing the Process control Program are clearly established and accomplished; 4.1.1.4 That personnel ;eive appropriate training and are i qualified for their tuspective duties; l
4.1.1.5 Procurement of materials and supplies required for implementation and maintenance of the Process Control ,
Program; I
4.1.1.6 Operation and maintenance of radwaste systems; f I
4.1.1.7 Inspection of Radwaste activities; and 5
[
4.1.1.8 Adequate staffing and sufficient resources for efficient and economic operation of the Process Control Program. f i
4.2 Radiation Protection Superintendent
[
4.2.1 The Radiation Protection Superintendent is responsible for ;
the overall effective management of the plant Process Control I Program. The Radiation Protection Superintendent ensures I i
that changes are initiated to the Process Control Program '
procedures when necessary and that appropriate Health Physics 4
support is provided. :
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Administrativa Procsdura RW-1-210 Process Control Program Revision 1 4.3 Plant Radwaste ingineer-Nuclear 4.3.1 The Plant Radwaste Engineer who reports to the Radiation Protection Superintendent holds key responsibilities for implementation of the Process Control Program such as:
4.3.1.1 Data collection, trend analysis, long-tern planning, and probles solving for the plant Process Control Program; 4.3.1.2 Managing radwaste solidification, dewatering and packaging; 4.3.1.3 Preparing proceduren for solidification, dewatering and packaging; 4.3.1.4 Interfacing with other groups as necessary to analyze and resolve problems relating to the Process Control program such as the design of Radwaste Systems and Equipment; 4.3.1.5 Preparing periodic reports summarizing the Process Control Program.
4.4 Operations Superintendent 4.4.1 The Operations Superintendent is responsible for the effective i
operations of permanent plant radweste systems and will coordinate radwaste activities with the radwaste department.
6
Administrctiva Precadura RW-1-210 Process Control Program Revision 1 1
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i 4.5 Chemistry Engineer-Nuclear 4.5.1 The Chemistry Engineer-Nuclear is responsible for interfacing with the Radwaste Engineer on items or problems relating to radwaste processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.
4.6 Plant Quality Manager 4.6.1 The Plant Quality Manager is responsible for the review of plant Process Control Program procedures.
4.7 Nuclear Services Manager 4.7.1 The Nuclear Services Manager is responsible for providing the following services:
4.7.1.1 State-of-the-art technical advise, support, and assistance as required; 4.7.1.2 Licensing and regulatory compliance support; and 4.7.1.3 Appraising the Waterford-3 Process Control Program and recommending improvements.
4.7.2 The Nuclear Services staff interfaces directly with the plant staff in providing these services.
4.8 Corporate Quality Assurance Manager 4.8.1 The Corporate Quality Assurance Manager is responsible for assessing the implementation and effectiveness of the quality assurance aspe:ta of the Process Control Program through regular audits sad selective monitoring of activities.
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Administrativa Prcesdure RW-1-210 I Process Control Program Revision 1 5.0 PROCEDURE i,
5.1 Program Description 5.1.1 Solidification Systes
Description:
Waterford 3 utilizes vendor supplied portable solidification
- equipment for radioactive waste solidification. References 2.2.1 through 2.2.11 provide a general description of respec-l tive vendor solidification processes and process control t
. . features; Reference 2.2.12 describes the method which will be utilized to classify wastes in accordance with 10CFR61; and i
1 Reference 2.1.1 through 2.1.7 are Waterford 3 documents which either Laplement or describe activities which provide reason-able assurance that wastes are solidified or dewatered in accordance with all applicable regulations and criteria.
5.1.2 Sources of Waterford 3 Solidification Feeds:
The solidification system will be used to process resins, evaporator bottoes and boric acid concentrates. During resin !
solidification, vendor equipment will be connected to both 7 the Resin Weste Management System outlet and dewatering inlet t
i to allow for the transfer of resin and the dewatering of the l l liner. Vendor equipment will be connected to the Solid waste l Management System outlet when avaporator bottoes from the l
radweste evaporator and boric acid concentrates from the l Boron Management System evaporator are to be solidified.
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Administrativa Pecccdura RW-1-210 Process Control Program Revision 1 5.2 Solidification Process Parameters:
5.2.1 Solidification formulas and solidification process parsaeters are incorporated into the applicable vendor process control progree. No exceptions or deviations from vendor supplied procedures or topical reports are anticipated. The formulas are used to calculate the ratio of waste, cement, water and other reagents required to achieve an acceptable solidified product. Compatibility requirements of the waste stress with respect to the solidification media are described in the vendor process controls program. Waste stream parameters are adjusted as necessary to meet these requirements.
5.2.2 Test solidifications are performed on waste stream samples to verify vendor calculated solidification formulas. Plant procedures describe the frequency for performing test soli-difications and establish the acceptance criteria for the test solidifications in accordance with Technical Specification 3/4 11.3.
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Administettiva Prec:durs RW-1-210 l
Pr:c:s3 Ctstral Pesgram Revision 1 l i
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i 5.3 Administrative Controls i i i i ,
5.3.1 Administrative controls utilized to insure compliance with !
applicable state and federal regulations and burial site l
criteria are detailed in the radioactive waste solidification l i surveillance procedure (s). These implementing document (s) j for radioactive waste solidification and dewatering describes l the requirements which must be met prior to processing radio- ,
l active waste, as well as the condition of the solidified i i ,
or dewatered waste. Test solidifications, full scale calcula- ,
l tions and operation of the solidification equipment are l
performed by vendor personnel. Dewatering operations will be I
! performed by vendor personnel or by qualified Plant staff.
f Plant staff provides Health Physics and Quality Assurance [
l coverage, operates plant radioactive waste systems, collects f waste stream samples and performs isotopic analyses. Copies of all referenced documents are available on site for use by -
t personnel engaged in solidification activities. !
i i 5.3.2 Changes to this Process Control Program shall be described in j the semi-annual Radioactive Effluent Release Report for the ,
4 i
] period in which the change is made, in accordance with Techni- j cal Specification 6.13.2.
i 5.4 Waste Characterization and Classification [
t 5.4.1 Weste Classification i
3 5.4.1.1 Solidified wastes are classified in accordance with
! the requirements of 10CFR61.55, as implemented by 1
l reference 2.2.12 and plant waste classification and :
characterisation procedure (s). l I
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V Adminictretiva Prscadura RW-1-210 Pete :s Ceatrol Prsgram Rsvision 1 5.1.4.2 Annual analysis will be performed on the waste streams to determine the isotopic abundance of gamma emmitting isotopes in the streams. Scaling factors for the non gamma enmitting and transuranic consti-tuents will be developed from this annual analysis.
The activity of each radionuclide in the solidified waste will be determined by a calculational method
- employing the percent abundance and scaling factors with a dose to curie conversion factor as described in reference 2.2.12.
5.4.2 Waste Characteristics 5.4.2.1 Solidified wastes will meet the characteristics of 10CFR61.56(a) and (b). Waste containers will be labelled to identify the waste class.
> 5.4.2.2 The manifesting requirements of 10CFR20.311 are implemented and records are maintained in accordance with 10CFR71.91.
5.5 Quality Assurance
, h I
5.5.1 Quality Assurance related activities for the Radioactive Weste Program are implemented as described in the Nuclear
- Operations Manageneet Manual (Reference 2.1.7). These activities provide verification that the solidified wastes meet applicable state and federal regulations and burial site ;
criteria.
6.0 ATTACHMENTS t
NONE I e
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_ . _ _ . _ _ _ _ _ ~. -_ _
1 ATTACHMENT 4 0FFSITE DOSE CALCULATION MANUAL HP-1-230, REVISION 4
WATERFORD 3 SES PLANT OPERATING MANUAL I OUISIANA POWER & LIGHT NN POM VOLUME 13 HP-1-230 POM SECTION 3 REVISION 4 l
FOR CU/ UTY ?: . CCTING ACTIVITtEd i i ,
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l SURVEILLANCE PROCEDURE OFFSITE DOSE CALCULATION MANUAL l
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l PORC Meeting No. 8[Y8 Reviewed:p hk(A,%
PORC tairma N
Approved: %
/php Plant Manager-Nuclear Approval Cata
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Effective DatE
it. d .e. C .: & a-3;,, a cy: HP-1-230 - Offsite Dose Calculation Manual (Rev. 4) r"?.C W he PC2C has :sviaved -'da 1:ss and datar=1=ed tha: a saf a 7 avaha:1..n was perfs -.ad !
(as appilkaala), that an um=aviaved saf scy questic d:as not exts: (as avvi'-=kla). !
-hat a changs :s the T^d ' Sp d'd-=tians is em: :squi:ad. and tha zuelaa sata 7 1s/vas act aaversaly affac.ad. i l
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- 1:aa is W=d f..r approval? 6 123 O so
- '* 1:aa requ1=as 32C/3EC review prior to 1=plammata. dan! C TIS -E 3C
- yes, ensure doc = mansard.=a ..,y..ug :sview is at.achad.
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1:ss requiras 4 ravise y=1st to FM-N approval? C TZ3 $ NC CA ..e a 2a,1a d y ^'/# c 4/A--
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Aspected by M *A""! //)//l Pian: .~.an ge e+4ue.l.aar T.-1-004. Revisica 6 13 Attachmen: - -6.1,(1 of 1) --- ---
E571' 2 C07 3 Sa:.:.
HP-1-230 - (Change 1) Offsite Dose Calculation Manual (Rev. 4)
L % "4 CT* !
? CRC R:. u J '
The PORC has reviaved :his 1:a= and da:ar d ed :ha: a safa:7 avalus:1 = vas perfor=ed (as applicabla), :ha: a= unraviaved safa:7 ques:1c= dcas no: exist (as applicable),
tha: a changa to the Tec M -si Specifica:1c=s is =c: requirad, and that nuclear safary is/vas =c: advarsely affac:ad. j l
' ORDER REC 0ldfEIDC 07 PCRC MDf3I1 PCRC MCf3ER ?CR A??ROVAL DA'"I RET S SIGNA L"RI TI.5 i NO I i
Ea1= ana=ca Superi=:anda== l Cparatic=s i Super 1=:anden: p j ,%
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Rad 12:1== Pro:actics. /
Supart==anda== 7 '[13/$ 6 5.a=aa?" v 66r ;
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Manarer 00Jh N, +m &?p-L A PCRC Esating No. @b4 I:ma No.. 46 Da:a S~<C f - f 5 This 1:a= is race-Mad for appr= val? @ TIS NO This 1:a= requires SEC/NEC ravias prior :s i pla===:2:1 =? O TzS E no If yes, a= sura docu=a= stic= supper:1=g reviav is a:: ached.
This 1:a= requires QA review prior :o PM-N approval? C TIS i
@' NO CA ?E7TZ*2 Reviewed by [ DATI M/.#
Corpora:a QA Ma= agar
?? AN* M427ACER-iUCLEAR APSROVAL {RETER TO 5.4.12.1)
Cc==a=:s:
Approved by I Fla==
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Otangar-Nuciaar DATE [lkD l
UNT-1-004, Revisio: 6 18
WATERIORD 3 SES .
PLANT OPERATING MANUAL Check Block Below CHANE/ REVISION /DELITION REQUEST [FOM l((PORC-S/C Procedure No. N 0-I-2'5 O Title 0 4 s,'/c h o rg Ca lc Jd. e n (if different from approval date) ^ ' ' I
- Effective Date Comolete A 3, and C A. Change No. l l Permanent l[lDeviation Espiration Date
- 3. Revision No. N C.
Deletion l[ LYES %NO DESCRIPTION OF CHAN E OR REVISION T-133 a d d e. d Yo knab '
'i5 Co l o m n a <-
Reca A Luf i
REASON FOR CHANGE. REVISION, OR DELETION 1- lb l \e Z + c, G F dor,% wurb () r c a e s s . n .-
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Sa.+;:. L a u 4+ L,,bs
< v RECUIRED SIGNATURES ORIGINATOR N DATE J C-/ ! ? $
/ '
Sirm REmv /
Does this change, revision, or deletion: 1
- 1. Change the facility as described in the FSAR? YES No V
- 2. Change the procedures as described in the FSAR? YES NO #
- 3. Conduct tests / experiments not described'in the FSAR? YES NO !
- 4. Require a change to the Tecnnical Specifications? YES NO -
1 If the answer .a any of the above is yes, complete and attach a
- 10CFR50.59 Safe Evaluation. /
SAFETT REVIEW N DATE 3'1/!Pd
/ l TECHNICALREVId b M M- b u d DATE 84//Nf 20UP HEAD REMW b3W7/M '
DM 3/n'/.ts
- DATE TEMPORARY APPROVAL * (SRO) ;
TEMPORARY APPROVAL
- DATE
{
- Temporary approval sust be followed by Plant Manager /APM-N - Nuclear approval within 14 days. l UNT-1-003 Revision 8 43 Attachment 6.7 (1 of 1)
....__.-_._-.._--._-.-l
l i4ATI3 FORD 3 SES l PLANT OPERATING MANUAL Check Block Below i CHANGI/ REVISION / DELETION REQUEST PCM ((lPORC-S/C Procedure No.1-10 I '130 Title Of cc. t , D c.s - C[I mieJ4T.e I b (
l Effective Date (if different from approval date) '
t C solete A, B, and C [
A. Change No. h!A l~lPermanent l[lDeviation F.xpiration Date j
- 3. Revision No. Y C. Deletion l[lYIS (INO DESCRIPTION OF CHANGE OR REVISION ,
Lt e cc- re tt < Civis i on of Ya.hle,s i em M k! a ar e, % [
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l REASON FOR CHANGE, REVISION, OR DELETION !
A n n v a.l Lo ^el
- (he 0ensvs den 4.'[loc/ ne 4 54 mal; m Jo e u. 4 '. o n s ', M e. e cho_nne > !
re s.$ 9 shd hv ' M R C- d !
U l l RECUI3EL SIGNATURES i ORIGINATOR . M e4 DATI // 'Jo - lr h SAITTT REVIIW ! !
Does this change, revision,'or deletion: !
t
- 1. Change the facility as described in the FSAR? YIS NO 7 i
- 2. Change the procedures as described.in the FSAR? TES NO - f
- 3. Conduct tests / experiments not described in the FSAR? YES NO - l
- 4. Require a change to the Technical Specifications? YES NO -
[
If the answer to any of the above is yes, complete and' attach a p 10CFR50.59 Safety Evaluation.
SAFEn* REVIIW e DATI // 2Y TECHNICAL REVIIW b bb//b DAII /W -8$ I GROUP HEAD REVIIW DATI /-23-25~
TEMPORARY APPROVAL * (SRO)
O DATE [
TEMPORARY APPROVAL
- DATE
- Temporary approval sust be followed by Plant Manager /APM-N - Nuclear approval within 14 days.
UNT-1-003 Revision 8 43 Attachment 6.7 (1 of 1) !
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Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 PREREQUISITES 4.0 PRECAUTIONS AND LIMITATIONS 5.0 INITIAL CONDITIONS 6.0 MATERIAL AND TEST EQUIPMENT 7.0 ACCEPTANCE CRITERIA 8.0 PROCEDURE 8.1 Site Characteristics 8.2 Radiological Environmental Monitoring Program 8.3 Radiological Environmental Monitoring Interlaboratory Comparison Program 8.4 Liquid and Gaseous Radwaste Block Flow Diagram 8.5 Liquid and Gaseous Waste Sampling and Analysis 3
8.6 Dose Calculations Due to Liquid Effluents 8.7 Determination of Alare/ Trip Setpoints for Liquid Monitors 8.8 Representative Sampling of Liquids 8.9 Projecting Dose for Radioactive Liquid Effluents 8.10 Dose Rate Due to Gaseous Effluents 8.11 Air Dose Calculations Due to Noble Gases 8.12 Dose Calculations Due to Radioiodines and Radioactive Materials in Particulate Form 8.13 Determination of Alarm / Trip Setpoints for Gaseous Monitors 8.14 Projecting Dose for Radioactive Gaseous Effluents 8.15 40CFRI90 Dose Evaluation r
1
Surveillance Procedure HP-1-230
~
Offsite Dose Calculation Manual Revision 4 9.0 SETPOINTS 10.0 ATTACHMENTS [
10.1 Annual Average Dispersion and Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary (Table 1) (1 page) 10.2 Radiological Environmental Monitoring Program (Table 2)
(2 pages) 10.3 Sample Location Table (Table 3) (9 pages) 10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) (1 page) 10.5 REMP Sample Locations Within 2 Miles of Waterford 3 (Figure 1) (1 page) 10.6 REMP Sample Locations Within 10 Miles of Waterford 3 (Figure 2) (1 page) 10.7 REMP Sample Locations Within 50 Miles of Waterford 3 (Figure 3) (1 page) 10.8 Liquid Waste Management System Effluent Sources and Release Pathways and Points (Figure 4) (2 pages) 10.9 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources, and Exhaust Release Points (Figure 5)
(1 page) 10.10 Open Terrain Correction Factor (Figure 6) (1 page) 10.11 Site-Related Liquid Dose Factor (Table 5) (1 page) 10.12 Bioaccumulation Factor for Freshwater Fish and Invertebrate and Ingestion Dose Factors for Adults (Table 6) (5 pages) 10.13 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble ,
Gases (Table 7) (1 page) 10.14 Inhalation Dose Factors for Child (Table 8) (3 pages) 10.15 Values of L-Theta-V (Table 9) (6 pages) 10.16 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R (Table 10) (19 pages) 10.17 Relative Deposition for Ground-Level Releases '
(All Atmospheric Stability Classes) (Figure 7) (1 page) 2
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 10.18 Annual Average Dispergion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) (1 page) 10.19 Annual Average Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary (Table 12) (1 page) 10.20 ODCM Technical Specifications Cross-Reference (Table 13)
(1 Page) 11.0 COMMITMENTS AND REFERENCES A
LIST OF EFFECTIVE PAGES Title Revision 4 1-102 Revision 4 h 3,s u.y 1 3 5
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Surveillance Procedure HP-1-230 Offsite Dose Calculation Manua'l' Revision 4 1.0 PURPOSE 1.1 This document provides: (1) the general characteristics of the Waterford 3 site; (2) the detailed Radiological Environmental Moni-toring Program (REMP); (3) the description of the Radiological Environmental Monitoring Interlaboratory Comparison Program; (4) the liquid and gaseous radwaste block flow diagram; (5) the Radioactive Liquid and Gaseous Waste Sampling and Analysis Programs; (6) the general methodology to be used to calculate dose to individuals due to releases of radioactive gaseous and liquid effluents from the Waterford 3 site; (7) the general methodology to be used to calculate effluent monitor setpoints and allowable release rates to ensure compliance with the Waterford 3 STS, 10CFR20, and 10CFR50 critcria; (8) the methodology to be used to ensure representative sampling of liquids; and (9) the methodology to be used to comply with 40CFR190 criteria.
1.2 The Offsite Dose Calculation Manual (ODCM) follows the general models suggested by NUREG 0133 (Nov., 1978) and Regulatory Guide 1.109 (Mar., 1976). However, alternate calculation methods from those presented may be used provided the overall methodology is acceptable and consistent with regulation or provided the alternate methodology is conservative. In addition, the most up-to-date dose conversion factors and bioaccumulation factors may be substituted in lieu of Regulatory Guide l'.109 values.
1.3 Actual step-by-step dose calculations will be performed by in-plant procedures which are consistent with the methodology presented in
~ this document.
2.0 REFERENCES
2.1 Waterford SES Unit 3 STS (Standard Technical Specifications), Chapter 16 of Waterford 3 FSAR ,
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Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 i
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2.1.1 Technical Specification Section 3/4 11.1 !
2.1.2 Technical Specification Section 3/4.11.2 4 2.1.3 Technical Specification Section 3/4.11.4 i
2.1.4 Technical Specification Section 3/4.12.1 ;
5 t
. 2.1.5 Technical Specification Section 3/4.12.3 i
l 2.1.6 Technical Specification Section 6.14.1 ,
12.1.7 Technical Specification Section 6.14.2 t 9
2.1.8 HP-1-215, NRC Radiological Reporting Requirements ;
t i '
2.2 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric j t
Transport and Dispersion of Gaseous Effluents in Routine Releases of l Gaseous Effluents from Light-Water-Cooled Reactors, July 1977 i 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of Ef- [
fluents from Accidental and Routine Reactor Releases for the Purpose l of Implementing Appendix I, April 1977 l 1
2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man' f
from Routine Releases of Reactor Effluents for the Purpose of .
Evaluating Compliance with 10CFR Part' 50, Appendix I. Revision 1, l
October, 1977 ;
r 2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical i Specifications for Nuclear Power Plants, October 1978 i
2.6 . Title 10, Code of. Federal Regulations, Parts 20, 50 and 100, Latest Edition F 5 ,
, , . ,w, y . - - .m.. ..,.- , p - ,--r y . , . - . . , , . .,
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 2.7 Title 40, Code of Federal Regulations, Part 190, Latest Edition 3.0 PREREQUISITES NONE 4.0 PRECAUTIONS AND LIMITATIONS References 2.1.6 and 2.1.7 should be satisfied at all times 5.0 INITIAL CONDITIONS Reference 2.1.6 should be satisfied prior to implementation.
6.0 MATERIAL AND TEST EQUIPMENT NONE 7.0 ACCEPTANCE CRITERIA NONE 8.0 PROCEDURE 8.1 SITE CHARACTERISTICS '
Waterford 3 SES is located on the west (right descending) bank of the Mississippi River at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of Killana and Taft.
6
l Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 The geographic coordinates for the Waterford 3 reactor are Latitude 29' 59' 42" North, and Longitude 90* 28' 16" West. Based on the UTM (Universal Transverse Mercator) Zone 15, the UTM coordinates are Northing 3,320,743 meters and Easting 743,962 meters.
The Mississippi River is the closest prominent natural feature to Waterford 3, while other important natural features include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchar-train, about 7 miles northeast of the site. The land slopes gently from its high points near the Mississippi (10-15 ft. above mean sea level) to extensive wetlands located 1.5 to 2.5 miles inland from the river.
Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford 3 site are several large industrial facilities, including Waterford 1 and 2 (0.4 miles northwest of the site), Little Gypsy Steam Electric Station (0.8 miles northeast of the site, across the river from Waterford 3), Beker Industries, a fertilizer manufacturer (0.6 miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and Union Carbide, a chemical manufacturer (1.2 miles east-southeast). . Louisiana Power & Light Company (LP&L) owns and operates the above-mentioned steam electric stations.
A map of the UNRESTRICTED AREA and SITE BOUNDARY for radioactive ef-fluents (Figure 5.1-3) is provided in the STS. LP&L will have full control of all activities conducted within the exclusion area boundary of the Waterford 3 site. All of the property within the designated exclusion area is owned by LP&L with the exception of the bottom lands below mean low water of the Mississippi River.
LP&L owns, in title, all surface rights within the exclusion area boundary of the plant. There is presently no intention to allow ex-ploration for subsurface minerals from points on the surface of the exclusion area.
7
t Survaillance Procedure HP-1-230 [
Offsite Dose Calculation Manual Revision 4 l i
t The Mississippi River, Louisiana Highway 18, the Missouri Pacific [
Railroad right-of-way, and the west (right descending) bank levee of the Mississippi River constitute traversals of the site exclusion j area as allowed by 10CFR100.3 (a). Refer to the Waterford 3 Emergency ;
i Plan Implementing Document for the arrangements which have been made j to give LP&L authority and control over these traversals. (Note that ;
Louisiana Highway 3127 does traverse the SITE BOUNDARY but not the -
exclusion area. However, LP&L does have the authority to control l this traversal in accordance with the Waterford 3 Emergency Plan {
Implementing Document.) l E
r i In addition to Waterford 3, there are two fossil-fueled units, f Waterford SES Units 1 and 2, which are owned by LP&L and which are -
within the site exclusion area. The plant staff for these two units !
t consists of about 60 people. Since this includes workers assigned j to shifts, it is a conservative estimate of the maximum number of !
fossil plant personnel that would be within the exclusion area at t any given time. Evacuation procedures for Waterford SES Units 1 and l 2 are described in the Waterford 3 Emergency Plan Implementing Document. l l
i A portion of the land within the SITE BOUNDARY is utilized for
- 1. e agricultural activities. Farmers presently work the land but j can be expected to actually be in the field less than 10 percent of i I
the time.
i Fishing in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be ex-pected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area. .
I 1
r 8 [
1
. ._. _ ~_ _ _ - . , _ _ _ , - _ - _ . . . . . . - ., . .
. Survaillance Procedure HP-1-230 i t
Offsite Dose Calculation Manual Revision 4 l 1
l i !
Texaco maintains a gas valve station east-southeast of the Waterford j 3 SES island structure just within the radius of the exclusion area. ;
This valve station is automated and requires only periodic monthly ;
a maintenance involving,- typically, two persons. ' Evacuation procedures j for these maintenance workers are described in the Waterford 3 !
Emergency Plan Implementing Document. f
- i. l i
i
- The Waterford property is shown in Figure 5.1-3 of the STS and !
l includes 3,561.3 acres. The plant area is about 48 acres and is r
defined as including the fenced area immediately adjacent to r Waterford 3. The site area is shown in Figure 5.1-3 of the STS j along with principal station structures and nearby features. The j site' includes only station structures and does not include any l
) residential, recreational, or other industrial structures. There is f f
. a visitor center-approximately 1.0 mile SSW of the plant. -
The SITE BOUNDARIES for establishing effluent release: limits along !
with radioactive effluent release points are given in Figure 5.1-3 l l
of the STS. The nearest distances to the boundary line are shown in
(
Table 1 of this procedure. The release point elevations for gaseous ;
i
- effluents are provided in Figure 5.1-3 of-the STS.
i' ;
- i i
The. restricted area,. defined.for the purpose of controlling ingress' j into and egress from the site, coincides with the plant area which !
is enclosed by the plant perimeter fence. !
1 i
f v
I
-?
+
s a
f.
i g % 6
.f 9
4
[
Survaillanca Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 For the purpose of establishing effluent release limits in accordance with 10CFR20 and Appendix I to 10CFR50, the concept of the restricted area, as defined above for the purpose of ingress and egress control, is not applicable. The effluent release limits are established in order to ensure that: (1) the concentrations of the radionuclides in gaseous effluents discharged from the plant stack and exhaust systems do not result in exceeding the limits outside the site boundary set forth in Table II, Column 1 of Appendix B to 10CFR20; (2) the concen-
- tration of radionuclides in liquid effluent at the unrestricted area boundary does not exceed the limits set forth in Table II, Column 2 of Appendix B to 10CFR20; and (3) the cumulative liquid and gaseous radionuclide releases do not result in exposures to individuals outside the UNRESTRICTED AREA or SITE BOUNDARY in excess of the limits set forth in Appendix I to 10CFR50.
1980 population by annular sectors within 5 miles of Waterford 3 can be found in the Environmental Report. Population was estimated for 1977 and projected for 1980. The methodology for estimating and projecting population is described in detail in section 6.1.4.2 of the Environmental Report. The closest town to Waterford 3 is Killona, 0.9 miles west-northwest. Other towns near the plant include Norco 2.5 miles east; Hahnville, 3 7 miles east-southeast; and Laplace, 4.7 miles north. There are also smaller settlements and homes along both banks of_the river, the nearest such place to Waterford 3 being Montz, 1.0 mile northeast.
8.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM y.
This section satisfies Surveillance Requirement 4.12.1 of the Waterford 3 STS.
a
.10
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 i Table 1 shows the average annual dispersion parameters for areas at or beyond the exclusion area boundary. This table will be subject to change based on the annual land-use census results. Tables 2, 3 and 4 are the detailed Radiological Environmental Monitoring Program, the Sample Location Table, and the sector and zone designations for the sample locations, respectively. Figures 1, 2 and 3 show the sample locations for samples within 2, 10 and 50 miles of Waterford 3, respectively.
- Deviations are permitted from the required sampling schedule if ,
specimens are unobtainable due to hazardous conditions, seasonal ;
unavailability, malfunction of automatic sampling equipment and other legitimate reason's. If specimens are unobtainable due to i sampling equipment malfunction, every effort shall be made to ;
complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be docu- ,
mented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical to continue to obtain samples of the media of choice at the most 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.
8.3 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON -
PROGRAM This section satisfies Surveillance Requirement 412.3 of the Waterford 3 STS. 1 11
-.4 - y .y. ,- - , .- -, _ s._ .--
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 Quality assurance in radiological environmental sampling will be maintained through participation in the Environmental Protection Agency's Radiological Laboratory Quality Assurance Program. The summary of results will be presented in tabular form and will detail the type of analysis, the preparation (collection) date, the date the results are returned, the mean of the analyses (usually tripli-cate), the standard deviation, the date the values are released for information, the known value, the three standard deviation limit, and a two standard deviation /three standard deviatica warning / action flag. If the sample analysis indicates results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report is submitted.
8.4 LIQUID AND GASEOUS RADWASTE BLOCK FLOW DIAGRAM This section of the document presents the block flow diagrams for the radwaste systems. Any modifications to the radwaste systems should be documented in the ODCM. In order to obtain a more detailed description of the various components, see the appropriate sections of the FSAR. Figures 4 and 5 show the existing radwaste systems.
8.5 LIQUID AND GASEOUS WASTE SAMPLING AND ANALYSIS 8.5.1 Liquids 8.5.1.1 At Waterford 3 there are four liquid holdup systems that should always contain detectable activity.
These liquid radiological effluent batch release systems include:
12
.d
Survaillance Procedure RP-1-230 Offsite Dose Calculation Manual Revision 4 i
A. Boric Acid Condensat- (BAC) - four tanks -
B. Waste Condensate (WC) - two tanks C. Laundry Waste (LW) - two tanks l D. Waste Tanks (WT) - two tanks i i
8.5.1.2 In addition to the tanks above, there are other ;
holdup tanks and sumps that may contain detectable l i
i r
activity. These tanks and sumps include the i following:
I
. E A. Regenerative Waste Tank (RWT) - one tank ;
B. Filter Flush Tank (FFT) - one tank C. Turbine Building Industrial Waste Sump (TBIWS) -
two sumps f D. Dry Cooling Tower Sumps (DCTS) - two sumps !
t NOTE If flow to the sump is isolated and volume of release is known, sump discharge may be treated as'a' batch i release rather than a continuous release.
i P
k i
i s
L b
l Surveillance Procedure HP-1-230 l Offsite Dose Calculation Manual Revisida 4 8.5.1.3 If the contents of the RWT or FFT contain detectable radioactivity, no discharges from these tanks shall 4
be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to the liquid radwaste treatment system. The TBIWS shall be required to be sampled and analyzed if any of the following condi-tions exists: (1) primary to secondary leakage 2
is occurring or (2) activity is present in the secondary system, as indicated by either the steam generator blowdown monitor or secondary sampling and analysis; or (3) activity was present in the TBIWS during the previous four weeks. If none of these situations exists, then the sampling and analysis of this stream need not be performed. Sampling and analysis of the DCTS will be required only when detectable activity exists in the Component Cooling Water System.
8.5.1.4 There are two additional liquid radiological effluent continuous releases at Waterford 3. These include:
A. Circulating Water Discharge - Steam Generator Blowdown heat exchanger (CWD - SGB)
B. Auxiliary (Component) Cooling Tower. (Water) pumps (ACTP) 8.5.1.5 Sampling and analysis of the CWD - SGB will be required only when detectable activity exists in the secondary system.
4 8.5.1 6 Sampling and analysis of the ACTP discharge will be required only when detectable activity exists in the
! Component Cooling Water System.
a 14
Survaillance Procedura HP-1-230 Offsite Dose Calculation Manual Revision 4 8.5.2 Gases 8.5.2.1 Waterford 3 gaseous radiological effluent batch releases include:
A. Waste Gas Holdup Tanks (WGHT) - three tanks within the Gaseous Waste Management System (GWMS)
B. Containment Purge (CP) a .
8.5.2.2 Gaseous radiological effluent continuous releases should include:
A. The Fuel Handling Building (FHB) ventilation exhaust B. The Containment Purge (CP)
C. The Plant Stack (PS)
D. The Main Condenser Evacuation and Turbine Gland Sealing System (MCE &.TGSS) 8.5.2.3 For the MCE & TGSS, if no primary to secondary leakage exists, then only the RETS Table 4.11-2 gross beta or gamma analysis need be performed. If a primary to secondary leak exists and the release from the MCE & TGSS has not been released via the PS, then the sampling and analysis found in Table 4.11-2 must be performed. A continuous permit should be issued if detectable activity is released through the MCE and TGSS.
8.6 DOSE CALCULATIONS DUE TO LIQUID EFFLUENTS This section presents the calculated methods used for calculating liquid effluent doses in accordance with Surveillance Requirements 4.11.1.1.1, 4.11.1.2 and 4.11.1.3.1 of the Waterford 3 Standard Technical Specifications (STS).
15
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 NOTE The Waterford 3 Radiological Effluent Technical Specifications (RETS) are a subset of the Waterford 3 STS. For purposes of this document, RETS and STS are interchangeable.
m 8.6.1 The dose contributions for the total time period g{3A g
.should be determined by calculation at least once every 31 days and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarte.r.
These dose contributions should be calculated for all .adio-nuclides identified in liquid effluents released to che UNRESiRICTED AREA using the following expression.
n Dgg = AtgFgg{g A gg Cgg (1) m Dt *Ab1 D gg (2) where:
D t1
= the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for each liquid release in ares during time period (2)
D t
= the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for all (2) time periods a -
g{ A g in arem
- 16
)
Surveillance Procedure HP-1-230 '
Offsite Do'se Calculation Manual Revision 4 time period over which the a gg = the length of the 1 release is made, in hours C gg = the concentration of radionuclide (i) in undiluted liquid effluent during time period agg from any liquid release, in pCi/ml
-A = the site-related ingestion dose commitment factor to it the total body or any organ (t) for each identified
! nuclide (i) listed in Table 4.11-1 of the Waterford 3 STS in aree-el per br-pci (Table 5)
J the near field average dilution factor for C gg during
~
Fg =
any liquid effluent release. Defined as the ratio of l the undiluted liquid waste flow during release to the j average' flow from the site discharge structure to J
site boundary receiving waters.
Fg = liquid radioactive waste flow discharge structure exit flow i,
l The liquid radioactive waste flow is the maximum flow from.the
- effluent release. The discharge structure exit flow is the flow during disposal from the discharge structure release point into the receiving water body. For radionuclides not i determined in each batch or weekly composite, the dose.contri-4 bution to the curre.it calendar quarter cumulative summation may be approximated by using a ratio of concentrations based on the previous monthly or quarterly composite analyses. When the current quarterly composite is analyzed, these contribu-tions will'be updated as appropriate.
17 L
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 8.6.2 Equation (2) above for calculating the dose contributions requires the use of a dose factor, A it, f r each nuclide (i) which embodies the dose factors and dilution factors for the points of pathway origin. The adult total body dose factor and the adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:
Agg = K,(U,/D, + U gBFg) DCFig (3) where:
U, = 730 kg/yr. adult water consumption Dw = Dilution factor from near field area to potable water intake = 220 220 = ava Mississippi flow maximum discharge flow A = Composite dose parameter for the total body or critical it organ (t) of an adult for nuclide (i) for all appro-priate pathways (mrem /hr per pCi/ml)
~K, = Units conversion factor, 1.14E5 = los pCi/pci x 10 3 al/l 8760hr/yr Ug = 21 kg/yr, adult fish consumption BFi = Bioaccumulation factor for nuclide (i) in fish (pCi/kg per pCi/1) from Table A-1 of Regulatory Guide 1.109 (Table 6) 18
Survsillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 DCF ig = Dose conversion factor for nuclide (i) and organ (t) for adults (mres/pci). Values are from Table E-11 of Regulatory Guide 1.109 (Table 6)
Inserting the usage factors of Regulatory Guide 1.109 as appropriate into equation (3) gives:
A it = [(3.78E + 5) + (2.39E + 6)BF g] DCF it
(') -
8.7 DETERMINATION OF ALARM / TRIP SETPOINTS FOR LIQUID MONITORS Waterford 3 STS 3.3.3.10 and 3.11.1.1 require that the liquid ef-o fluent monitoring instrumentation alarm / trip setpoints be set so that the concentration of radioactive material released from the j site is limited to 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. (For dissolved or entrairied noble gases, the concentration shall be limited to. 2E-4 pCi/ml total activity.) This section presents the method to be used for determining setpoints in accordance with Surveillance Requirements of 4.11.1.1.2 of the Waterford 3 STS.
8.7.1 Determination of Liquid Monitor Setpoints 8.7.1.1 The calculated.setpoints for the liquid effluent monitors satisfy the following equation:
n (SF) (RF) (F + f)g 11C i (5)
C_~
TMPC (f) where; n
IC g = the undiluted effluent gamma concentration in pCi/ml c, i=1 for all radionuclides (1). The value will be derived from radioanalysis of liquid effluent to be released.
This value will be supplied for each liquid release.
19
Survaillence Precadurn HP-1-230 Offsite Dose Calculation Manual Revision 4 c= the setpoint, in pCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release. This setpoint represents a value which, if exceeded would result in concentrations exceeding the limits of 10CFR20, Appendix B, Table II. Column 2, to an UNRESTRICTED AREA.
. f= the liquid effluents flow as measured at the liquid effluent monitor location in gpm.
i F= the dilution water flow as determined via pump curves or other apropriate measures that determine currect plant operating configuration in gpm.
NOTE F is large compared to f; .'. F + f E F.
SF = Safety factor to ensure that the effluent limit is not exceeded. Actaal value is set by procedure (in the range 0.5 - 0.9).
RF = Release fraction allocated to this release (to be used only in situations of simultaneous or concur-4 rent release). ;
n C m C
- ibiMPC g
- jEl C
l = the undiluted nongamma MPC fraction for all MPC d j nongamma radionuclides (j) 20 t
- ~. ... , . . _ _ - . - - - - . . - . . . .- , - . . , , . ..
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 i
C i
i = undiluted gamma MPC g fraction for all ganna
@C i radionuclides (i)
= Maximus Permissible Concentration for the applica-MPC) ble nongamma-emitting isotope (j) from 10CFR20, Appendix B, table II, column 2.
MPC g = Maximus Permissible Concentration for the applica-1 ble gamma-emitting isotope (i) from 10CFR20, i Appendix B, table II, Column 2.
8.7.1.2 ,The values of C 1 and C) will be acasured for each release and the parameters for f and F will be -
3 supplied based on current plant operating configura-tions. The setpoint will be calculated in terms of pCi/a1 and the liquid effluent monitor will be adjusted as necessary to ensure that liquid releases are secured prior to exceeding limits specified in 10CFR20,. Appendix B, Table II, Column 2 to an UNRESTRICTED AREA.
Example:
Assume Cg = 3E-4 pCi/ml C) = 3E-4 pCi/ml f = 50 spe + 3.16E+3 al/sec F = 750,000 gym + 4.75E+7 al/sec MPCg = 2E-5 pCi/al MPC) = 3E-7 pCi/al 21
~, 9 - m - ,-# . _ . , - + - ~ , = - ----.w-- - g. e ,-%. .,e.* -,p ---. . - - - -y
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 3E-4 4
c = (f)TMPC 'TMPC = 2E-5 3E-7
, 3E-4 = IE+3 f
3E-4 pCi/ml)(4.75E+7 ml/sec) c _ ((3.16E+3 ml/sec) (1E+3) c = 4.51E-3 pCi/ml Then the SF and RF values can be applied; i.e., SF =
0.8 and RF = 1 because normally concurrent releases will not occur.
c = 3.61E-3 pCi/ml 8.8 REPRESENTATIVE SAMPLING OF LIQUIDS 1
8.8.1 Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling. Large volumes of.
liquid waste should be mixed in as short a time as possible and uniformly distributed prior to sampling. To determine the minimum mixing time for tanks from which releases are made, the following tests were performed prior to initial use for release purposes.
8.8.1.1 The tank was filled to a known volume.
8.8.1.2 A specific quantity of a' selected chemical and/or sediments was added to the tank.
8.8.1.3 Recirculation was initiated through the normal path.
8.8.1.4 Periodic samples was taken until equilibrium is reached. .
t 22
.,. r .~ __-y., , . - - - , - , - --
Survaillance. Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 i
t 8.8.1.5 The time observed to completely mix the tank is used as a minimum recirculation time prior to effluent ,
sampling. Records of the test will be maintained.
8.9 PROJECTING DOSE FOR RADIOACTIVE LIQUID EFFLUENTS l Technical Specification 3.11.1.3 requires that appropriate subsystems !
of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent j from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem j total body or 0.2 area to any organ in'a 31-day period. The following calculational method is provided for performing this dose projection.
At least once every 31 days, the total dose from all liquid releases i for the . quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. If this_ projected dose exceeds 0.06 arem total body or 0.2 mrem any organ, and the Liquid Waste Management System has not been operating,. it shall be operated, if operation would reduce the monthly projected doses below 0.06 mrem ;
s total body or 0.2 mrem any organ. (This is performed in accordance '
with Surveillance Requirements 4.11.1.3.1 and 4.11.1.3.2.) ,
'8.10 DOSE RATE DUE TO GASEOUS EFFLUENTS i This section presents the calculational methods used for calculating gaseous effluent doses in accordance with Surveillance Requirements ,
~
i 4.11.2.1.1 and 4.11.2.1.3 of the Waterford 3 STS.
b r
+ b 23 ,
i
_ _ . _ _.m. -,,
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 8.10.1 Real Time Meteorological input The instantaneous 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 values:
l 8.10.1.1 Release rate limit for noble gases:
n D0b=K'(X/Q)0viEl Ki (9)iv (6) n Des = K'(X/Q)0vi ib (bi
- 1*I i) (9)iv ()
8.10.1.2 Release rate limit for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days:
n DOI =(X/Q)0viEl Pig (Q)(y (8)
.where:
D 0b
= the instantaneous dose rate to the total body (b) due to noble gases in sector 0 for the release in mres/yr; not to exceed 500 mrem /yr D0s = the instantaneous dose rate to the skin (s) due to noble gases in sector 0 for the release in mrem /yr; not to exceed 3000 mres/yr 24-
- t. .. , . . . .
.- . . . n
s I
Surveillanca Procedure HP-1-230 l Offsite Dose Calculation Manu Revision 4 l l
i DOI = the instantaneous dose rate to the child thyroid (I) for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in sector 0 for the release in units of area /yr; not to exceed 1500 mrem /yr.
~K' = a constant of unit conversion, IE6pCi/pci.
, Kg= the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of mrem /yr per pCi/m 3 (Table 7).
L g= the skin dose factor due to beta emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m 3 (Table 7).
Mg= the air dose factor due to gamma emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m 3 (Table 7).
Pgg = the thyroid dose parameter for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days (i) for the inhalation pathway only, in ares /yr per pCi/m3 (Table 10, Page 2). The dose f.sctor is based on the most restrictive group (child) and most restrictive organ at the SITE BOUNDARY.
Pig = (child breathing rate of 3700 m 3/yr)(DFAg ) (K') where DFA g is the inhalation dose factor for each radio-nuclide from Table 8, 25
e i
Survaillance Procedure HP-1-230
, Offsite Dose Calculation Manual Revision 4
- r 1
b n
I = summation for all identified radionuclides ,
, g3 I
(Q)gy = the average release rate of noble gas or of Iodine-131, Iodine-133, tritium, and radionuclides in the parti-culate form with half-lives greater than 8 days (i) i during the time of release from all vent releases 7 (v). Value is averaged over one hour and is in units of pCi/sec.
L (X/Q)0v = the average atmosphere dispersion factor at the SITE B0UNDARY for the time of the release in sector 0 in 3
sec/m for all vent releases (v). When release time is greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the average shall be based on observations of windspeed and atmospheric stability taken at least every hour during the release, j (X/Q)0v " Lev /" ,
where:
i
" = the average wind speed determined at least hourly, during time of the release, 'in sector 0 , at 10 meters above grade, in m/sec .
t and, Lev = 2.032/r0I zj' 2.032 = (2/n)b divided by the width in radians of a 22.5*
sector. ,
t r the distance from the release to the receptor for 0=
each sector (0) in m, and provided in Table 9. i 26 i
tv v
-Survaillence Proctdure HP-1-230 Offsite Dose Calculation Manual Revision 4 I zj = the vertical (z) standard deviation of the materials in the plume, for stability class j, with a correc--
tion for additional dispersion within the building wake cavity, restricted by the condition that
\
2 I.zj = (ozj. + 0.5Dz2 /n) 5 /3 o zj furthermore, I.=4a zj zj when 2
(aj+0.5D/n)>4o,)
z and D, = _the maximum' adjacent building height (z) either up or downwind from the release point.
a,) = the vertical (z)' standard deviation of the material in the plume at the downwind distance for stability class J.
27
1 Surveillance Procedure HP-1-230
~
Offsite Dose Calculation Manual Revision 4 The (X/Q) values to be calculate'd using the above model will be adjusted to reflect the results of analysis of the straight line trajectory model-(Reference 2.2, R.G. 1.111, Sections C.1.c and C.2.c). This adjustment is accomplished by multiply-ing the (X/Q) values by the correction factors, found in Figure 6, which applies to areas with terrain features similar to those at the Waterford 3 site, NOTE The Radioactive Effluent Release Report, to be sub-mitted within 60 days after January 1, of each year, I
shall' include an annual summary of hourly meteorological data collected over the previous year. The meteorolog-ical conditions-concurrent with the time of release of i
radioactive materials in gaseous effluents, as deter-mined by sampling frequency and measurements, shall be
- used for determining the gaseous pathway doses.
i 8.10.2 No Real Time Meteorological Input (Used in Place of Real Time)
The dose rate due to' radioactive materials released in gaseous ,
4
- effluents from the site to areas at and beyond the SITE '
BOUNDARY shall be limited _to the following values and expressions:
4 8.10.2.1 Release rate limit for noble gases: ;
- n .
K':(X/Q),g{g KgQ1yi 500eres/yr. total body (9) i n- . .
K'(X/Q),gjg(L[+1.1M)Qiy 1 i 3000eres/yr. skin (10)
]
I .
3
< +
28 i
5
,- - - -m .,- 4 - - ,. ,e--.mn--,- y .-.-r,--- , , - , - , ,, . .n v-m . + - - -,,,.w,---
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 8.10.2.2 Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with hal(-lives greater than 8 days:
n .
K'(X/Q),ijg P it Oivs 1500 mrea/yr any organ (11)
Where:
Q,=
g the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec (X/Q),= 1.1E-5 sec/m3 in the ESE sector at 0.6 mile for all vent releases (v) (the highest calculated annual average dispersion factor at the SITE BOUNDARY)
NOTE All radioiodines are assumed to be released in elemental form.
l 8.11 AIRDOSECALCULATIONSDUETONOBLEGASEE This section presents the' calculational methods used for calculat'ing L noble gas-effluent dose to air in accordance with Surveillance t
l Requirement 4.11.2.2 of the Waterford 3 STS.
8.11.1 Real Time Meteorological Input-l; The air dose due to noble. gases released in gaseous effluents to areas at:and bey.lnd the SITE BOUNDARY will be determined by l the'following expressions:
i:- 29
'Surveillanca Procsdura HP-1-230 Offsite Dose Calculation Manual Revision 4 8.11.1.1 During any calendar quarter, for gamma radiation:
a m D
0y = (1.14E2)g{g (M g ) 3{g (at)) (X/Q)jev (9)ijv (12)
During any calendar quarter, for beta radiation:
n a D ep=(1.14E2)g{1(N)3{g(at)'(X/Q)jgy(Q)fjy g (13) 3 8.11.1.2 During any calendar year, for gamma radiation:
n a D
0y = (1.14E2) g{g (M g ) j{g (at)) (X/Q) Ov(9)ijv (14)
During any calendar year, for beta radiation:
n a D
gp = (1.14E2) g{g (N g ) ){g (at)) (X/Q) j0v(9)ijv (15) where all terms are as previously defined; and D
0y = the total gamma (y) air dose in sector 0 from gaseous effluents for the total time period (e.g.,
quarter or year) m jElAEj and not to exceed 5 mrad quarterly or 10 mrad yearly D the total beta-($) air dose in sector 6 from gaseous e$ =
effluents for the total time period (e.g., quarter or year) m J1E O')
and not to exceed 10 mrad quarterly or 20 mrad yearly yr.
1.14E2 =pCi (1 6 4 ) (8760hr.)
30
Survaillance Procsdura HP-1-230 Offsite Dose Calculation Manual Revision 4 e
1 (Q)q y = the average release rate of radionuclides (i) ,
during the time of release At. for vent releases (v) "
J i Atj= the length of the j time period over which (X/Q)gy ;
4 and Qg ) ,are accumulated for all gaseous releases (hour.).
Mg and Ng = the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (i) (mrad /yr per pCi/m3) (Table 7)
L (X/Q)jov = the average atmospheric dispension factor at,the site boundary for the time of the release (j), in sector (0), in sec/m 3 , for all vent releases (v).
f When release time is greater than one hour, the ;
average shall be based on observations of windspeed and atmospheric stability taken at least every hour i during the-release.
8.11.2 No Real Time Meteorological Input (Used in Place of Real Time) i The air dose due to noble gases released in gaseous effluents [
_ to areas at or beyond the SITE BOUNDARY will be determined by
, the following expressions when the real time meteorological ,
inputs are not applicable:
r t
8.11.2.1 During any calendar quarter, for gamma radiation:
n a :
D
=(1.14E2)(X/Q)ygjg(M)j{g(At)(Q)13y g j (16) [
During any calendar quarter, for beta radiation:
a m ;
D p=(1.14E2)(X/Q),g{3(N)){y(At)(Q)g),
g 3 (17) r r
31
Survrillanca Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 8.11.2.2 During any calendar year, for gamma radiation:
n m De = (1.14E2) (X/Q)y ({g(M)j{g(at)(Q)f),
i 3 (18)
During any calendar year, for beta radiation; n m D = (1.14E2) (x/Q)y g{g(N)){g(at)(Q)(3y g j (19) where all values are as defined previously; and D = the total gamma (y) air dose from gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad yearly.
D p = the total beta (S) air dose from gaseous effluents for the total time period and not to exceed 10 mrad quarterly and 20 mrad yearly. -
Qijy = the average release rate of radionuclides'(i) in gaseous effluent from all vent releases (v) in pCi/sec during the time period at..
J 3
(X/Q)y = 1.1E-5 sec/m in the ESE sector at 0.6 mile for all vent releases (v).
8.12 DOSE CALCULATIONS ~>UE TO RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM f This section presents the calculational methods used for calculating doses due to Iodine-131, Iodine-133, tritium, and radionuclides in '
particulate form in accordance with Surveillance Requirement 4.11.2.3 '
of the Waterford 3 STS.
L 4
I 32 l
Survaillanca Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 6
8.12.1 Real Time Meteorological Input The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-2 lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the following expressions:
8.12.1.1 During any calendar quarter for age group a:
n a D
0ta *(I*I'"')ib1(Rita)jb1(0 j) I( )0jv (9)ijv] (20) 8.12.1.2 During any calendar year for age group a:
n a D
0ta =(1.14E-4)ff3(Rita) jb1 (OUj ) {(w)0jv (9)ijvl (2I) where all terms are as previously defined; and D = the cumulative dose due to Iodine-131, Iodine-133, 0ta tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents, to an organ (t), of an individual (a), in sector 0, for the total time period:
m I At j=1 d not to exceed 7.5 mrem in any calendar quarter or 15 mres in any calendar year.
1.14E-4 = 8760hr.
1 F
33 i
i
(
Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 Rig, = the dose factor from each identified radionuclide j (i), for each applicable organ (t), and age group -
(a), in mrem /yr per pCi/m3 for the inhalation pathway [
2 and in mrem /yr per pCi/m -see for the food and ground f plane pathway from Table 10. For sectors with real pathways within 5 miles of the plant, the values of R g are used based on these real pathways; for sectors
{
with no real pathways within 5 miles from the plant, ;
Rg is used assuming that the cow-grass-milk pathway [
I exists at the 5-mile distance. (R g's were calculated using the methodology found in Reference 2.5, pages j 31-36.) !
?
W g3y
= dispersion parameter for time period (j) and release pt (v) for calculation of food pathway dose ,
W 8jv * ( N )0vj f r the inhalation pathway W
0jv = (D/Q)0vj f r the food and ground plane pathway where (yjQ)gy) is.as defined previously; and, I
(D/Q)0vj = relative deposition for the time period (at)), in sector (6), for release pt (v), in square meters. ,.
t When at) is greater than one hour, relative deposi-tion shall be based on observation of atmospheric stability taken at least every hour during at).
(D/Q)gy) =(0 2 )(r e) i I
i 34 N . -
-4 _ , m_.,, , . - . _ . , . - , _ .
7 Surveillanca Procsdura HP-1-230
[
Offsite Dose Calculation Manual Revision 4 i
where:
- . (0.3927)r6= are length of the 22.5* sector at distance r 0 I" l
meters, t
.a
~
f6= wind direction factor; equals 1 if wind in hour t is into sector 0; equals zero if wind is not into sector
^
6.
dev = relative deposition rate for ground-level vent
, release (v) at distance (re ) in sector (0) for all '
stability classes of interest, (meters " ) taken '
i from Figure 7.
l 8.12.2 No Real Time Meteorological Input (Used in Place of Real Time) (
The dose to an individual from Iodine-131,. Iodine-133, tritium, .
2 and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and 3
beyond the SITE BOUNDARY will be determined by the following expressions:
8.12.2.1 During any calendar quarter:
I
?
4 ;
a D = 1.14E-4 At I R (22) ita ita v Oiv.
i=1 I
, 8.12.2.2 -During any calendar year:
n ita NvOiv D = 1.14E-4 At I R (23) l ita i=1 .
where all terms are as previously defined; and' j l At = the time. required for the release in hons for all releases per quarter or per year ,
i 35 o
Survaillence Procedura HP-1-230 Offsite Dose Calculation Manual Revision 4 D
ita
= the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in gaseous effluents; not to exceed 7.5 mrem quarterly or 15 mrem yearly Wy = the dispersion parameter for estimating the dose to an indi-
~
vidual at the controlling location for long term vent releases I
(v)
Wy = (X/Q), for the inhalation pathway from vent releases (v) in sec/m3, from Table 11 or Table 1, for the critical receptor.
Wy = (D/Q), for the food and ground plane pathways from vent releases (v) in m2, from Table 12 or Table 1, for the critical receptor.
8.13 DETERMINATION OF ALARM / TRIP SETPOINTS FOR GASEOUS MONITORS Waterford 3 STS 3.3.3.11 states that the radioactive gaseous ef-i fluent monitoring instrumentation alarm / trip setpoint be set to ensure that the limits of Waterford 3 STS 3.11.2.1 are not ex-ceeded. ,
i
't l
1 L
36 ;
7._ . ._ _.
g %
j Surveillance Procedure' HP-1-230 Offsite Dose Calculation Manual- Revision 4
- i. < ,
- i. 8.13.1 Setpoint Calculations for Gaseous Monitors i
l .
The' calculated high level alarm and. flow termination trip 4
l setpoints will be regarded as the' limiting conditions for the actual setpoint adjustments. The gaseous effluent radiation l
monitor setpoints are usually expressed in pCi/cc. For
- conservatism,' an administrative safety factor SF (% of dose i rate limit) will be. introduced into setpoint calculation. . To j
allow'for multiple' sources of release from different or common
! release' points, the allowable operating setpoints will be 4
controlled administrative 1y by allocating a percentage of the.
total allowable release to each release source (RF).
8.13.2 General Gaseous Setpoint Bases 1 Gaseous setpoints will be based on noble gas dose rate (less
!, than'or equal to 500 ares /yr total body, and less than or
~
! s
. equal to 3000. ares /yr skin).. Specifically, gaseous setpoints will be based'on the most limiting of the following equations:
l 8.13.2.1 Total Body i
J
~
q , (500 ares /yr.)(RF)(SF) }' , '
j (X/Q),(IE6pci/pci) n i I Ii Oiv
! c -, i=1 la , -
n S / ',
t l I i=1 Q'
I j' ,
- , v 1 l.
, Then, based,on maximum flow rate,. the monitor setpoint SN in uCi/cc can be calculated:
g n / ~ ' +
I-Q l
tb i SN = F e .
man c
< 37 i -
l .
L.
' Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 where:
F,,, = maximum effluent flow rate (cc/sec).
n I = summation of all nuclides considered.
i=1 Qtb = maximum release rate allowed to give limiting total body (tb) dose of 500 arem/yr (pCi/sec).
- K g= the total body. dose factor due to gamma emissions for each identified radionuclide (i) in units of mrem /yr per pCi/m 3 (Table 7).
Qgy = average release rate of isotope (i) from the release point (v) in pCi/sec.
RF = release fraction allotted to release point in consideration. '
(X/Q)y = 1.1E-5 sec/m3 (in the ESE sector at 0.6 mile). The sector l with highest value of annual average atmospheric dispersion factor at the site boundary for the release point (v) in i question. ,'
- SF = administrative safety factor to account for uncontrollable ,
variables (sampling, monitoring errors, etc.). Usually, the SF takes on a value between 0.5-0.8. ,
4 4
4 1
38
Survzillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 4 8.13.2.2 For skin
_ (3000 mrem /yr.)(RF)(SF) (25) 9 skin -
(X/Q)y(1E6pCi/pci) n I (Lg + 1.1 M )g Qty i=1 n
I O iv i=1 SN = 9 skin Faax where all terms are as defined above except:
Q skin = maximum release rate allowed to giie limiting skin dose of 3000 mrea/yr (pci/sec).
Lg= skin dose factor due to beta emissions for each identified radionuclide (i) in units of mres/yr per pCi/m3 (Table 7).
1.1 = conversion factor to convert frosi air to skin dose.
Mg= air dose factor due to gamma emissions for identified noble gas isotope (i) in units of arad/yr per pCi/m 3 from Table 7.
8.13.3 Gaseous Setpoint Calculations Based on Kr-88.
Since the noble gas dose rate is more limiting than the radioiodine dose rate, the init.ial monitor setpoints can be based on a conservative count rate using Kr-88 until operating experience is accumulated. To:a1 body dose will be more limiting than skin dose; therefore, the release limit would be:
39 o
Survaillrnce Proctdura HP-1-230 Offsite Dose Calculation Manual Revision 4 (500 mrem /yr.)(RF)(SF) (24a) r-88 ,
(X/Q)y(le6pci/pci)(KKR-88)
Then, based on maximum flow rate, the monitor setpoint SN in pCi/cc can be calculated:
SN =
r-8 ( 6)
- I max where:
F aax
= maximum effluent fl w rate (cc/sec)
NOTE
- To determine whether total body or skin dose is more limiting for Kr-88, equations (24) and (25) are solved for QKr-88' 8I"C"
- 1 "*# O Kr-88 is required to reach the total body limit of 500 meem/yr, the total body dose is more limiting.
8.14 PROJECTING DOSE FOR RADIOACTIVE GASEOUS EFFLUENTS l
Technical Specification 3.11.2.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment System be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a 31-day period, either:
0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
40 l
Survai11 tace Procsdure HP-1-230
~
, Offsite Dose Calculation Manual Revision 4 4
1 l
! The following calculational method is provided~for performing this dose projection. .
At least once every 31 days the gamma air dose, beta air dose and j
the maximum organ dose for the month-to quarter will be' divided by the number of days into the quarter and multiplied by 31. If these ;
, projected doses exceed any of the values listed above and the Gaseous I Waste Management System has not been operating, it shall be operated l
,. to reduce radioactivity levels prior to release. (This is performed v j in accordance with Surveillance Requirements 4.11.2.4.1 and ;
l "
j 4.11.2.4.2.)
.F 4
8.15 40CFR190 DOSE EVALUATION j i
i This section demonstrates compliance with Surveillance Requirements [
[ 4'.11.4.1 and 4.11.4.2 of the Waterford 3 STS. Specifically, the I
dose or dose comunitment to any MEMBER OF THE PUBLIC due to releases -[
of radioactivity and radiation from uranium fuel cycle sources shall !
t be limited to less than or equal to 25 ares to the total body or any >
l
, organ (except the thyroid, which shall be limited to less than or. )
equal to 75 ares) over 12 consecutive months. h i !
I Dose evaluations to demonstrate compliance with the above dose limits f
j need.be performed only if the quarterly doses calculated in sections !
l 8.6, 8.10, 8.11 and 8.12 exceed twice the dose limits of STS j 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a or [
- 3.11.2.3.b, respectively; i.e., quarterly doses exceeding 3 mrem to. .f*
I
- the~ total body (liquid releases), 10 ares to any organ (liquid !
. t
! releases), 10 mrad gamma air dose, 20'erad beta air dose, or 15 mrem !
i .
i to the thyroid or any organ from radiciodines and particulates ;
s (gaseous releases). Otherwise, no evaluations are required.
l !
t
- 41 ;
i ;
Survaillance Procedura HP-1-230 Offsite Dose Calculation Manual Revision 4 4
For the evaluation of doses to real individuals from liquid releases, 4
the same calculational methods as employed in section 8.6 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides by individuals who live and fish in the Waterford 3 area. The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radio-nuclide concentrations. For the evaluation of doses to real indivi-duals from gaseous releases, the same calculational methods as employed in sections 8.10, 8.11 and 8.12 will be used. In sections f 8.10 and 8.11, the total body dose factor should be substituted for !
the gamma air dose factor (Mg ) to determine the total body dose. f Otherwise, the same calculational sequence applies. More realistic f assumptions will be made concerning the actual location of real i '
individuals, the meteorological conditions, and the consumption of .
i food. Data obtained from the latest land use census should be used i to determine locations for evaluating doses. The results of the j j
Radiological Environmental Monitoring Program will be included in f f ,
determining more realistic doses based on actual measured radio-i l nuclide concentrations. {
i i
Cumulative dose contributions from direct radiation, from the reactor !
l unit, and from Radwaste Storage Tanks shall be-determined utilizing the results of routine plant perimeter surveys, TLD data,- or a E
. combination of both when necessary. '
f; I
i !
- 9.0 SETPOINTS I
I NONE i i t
10.0 ATTACHMENTS -
. F i 10.1 ' Annual Average Dispersion and Deposition Parameters For Areas At !
or Beyond the. Unrestricted Area Boundary (Table 1) l
- 42 ,
t
. , - , . ~ . - - . ._ . _ . . . . - . . , _ - - - . . - . _ _ . . , , _ _ ,_ . .. . . - _ , , , . . _ , - . , - , - - , _ _ - . ..,
Survaillance Procsdura HP-1-230 Offsite Dose Calculation Manual Revision 4 i
F 10.2 Radiological Envirocmental Monitoring Program (Table 2)
! 10.3 Sample Location Table (Table 3) !
F t
10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) [
i 10.5 REMP Sample Locations Within 2 Miles of Waterford 3 (Figure 1) t
{
f j 10.6 REMP Sample Locations Within 10 Miles of Waterford 3 (Figure 2) i 10.7 REMP Sample Locations Within 50 Miles of Waterford 3 (Figure 3)
I 10.8 Liquid Waste Management System Effluent Sources and Release j pathways and Points (Figure 4) 10.9 Gaseous Effluent Sources, Gaseous Waste Management Systems f Effluent Sources, and Exhaust Release Points (Figure 5) !
{ 10.10 Open Terrain Correction Factor.(Figure 6) f 10.11 Site-Related Liquid Dose Factor (Table 5) f i
i 10.12 Bioaccumulation Factor for Freshwater Fish and Invertebrate and !
l
-Ingestion Dose Factors for Adults (Table 6) -
10.13 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases !
(Table 7) ;
r I
10.14 Inhalation Dose Factors for Child (Table 8) 10.15 Values of L-Theta-V (Table 9) i 43 >
r
T Survailla.ce Procedure HP-1-230 Offsite D..se Calculation Manual Revision 4 10.16 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R (Table 10) 10.17 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) (Figure 7) 10.18 Annual Average Dispersion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) 10.19 Annual Average Deposition Parameters for Areas at or Beyond the
]
Unrestricted Area Boundary (Table 12) 10.20 ODCM Technical Specifications Cross-Reference (Table 13) '
i 11.0' COMMITMENTS AND REFERENCES i
r l
I I t
h
?
I l
f 3
P 44 :
Tedio 1 .
AIRIGAL AVERAGE DISPERSION (E/Q) AND DEP081 TION (D/Q) VALNB8 GROUNO LEVEL RELE45i, O N CORRICTED POR OPEN TERRAIN RECIRCULATION SPECIPIC POINTS OF INTEREST RELEASE TYPE OP OIRECTION OISTANCE I/O E/Q X/J 0/0 -
IG LOCATION (NILES) (NETER5) (SEC/CUS.NETER) (SEC/CUS.NETERI (SEC/ Cut.NETERI (PER SQ.NETERI NO DECAV '
2.260 DAV OECAV -
8.000 DAV OECAV UNDEPLETED UNDEPLETED DEPLETED ,
G NILE Cows E 3.30 5311. 3.4E-07 3.3E-07 2.FE-OF 3.9E-10 G NILE CON 5 NW 4.40 7081. 3.1E-07 2.9E-07 2 3E-0F 5.1E-10 G NILE GOATS ENE 0.90 1448. 6.5E-06 6.4E-06 5.FE-06 1.1E-08 G NILE GOATS E 3.30 5311. 3.4E-07 3.3E-OF 2.FE-0F 3.9E-10 G vtGETASLE GARDEN N 1.10 1770. 4.FE-06 4.FE-06 4.1E-06 1.1E-08 G vtGETAsLE GARDEN NNE 1.30 2092. 2.9E-06 2.9E-06 2.5E-06 5.8E-09 G WEGETABLE GARDEN NE 1.00 1609. 4.FE-04 4.FE-06 . 4.It-06 9.2E-09 G vtGETABLE GARDEN ENE 0.90 1448. 6.5E-04 4.4E-06 5.FE-06 1.1E-08 G vtGETASLE GARDEN E 3.20 5150. 3.6E-OF 3.4E-07 2.8E-07 4.2E-10 G WEGETABLE GARDEN ESE 2.30 3F01. 6.2E-OF 6.0E-07 5.0E-OF 9.6E-10 G WEGETASLE GARDEN SE 2.30 3701. 6.0E-07 5.8E-07 4.9E-07 1.3E-09 G WEGETABLE GARDEN W5W 1.40 2575. 1.4E-06 1.4E-06 1.2E-06 4.2E-09
! 6 WEGETABLE GARDEN W 3.00 1609 2.3E-06 2.2E-06 2.0E-06 F.3E-09
- 1448.
G vtGETABLE GARDEN WNW 0.90 5.5E-06 5.4E-04 4.8E-06 2.0s-08 G VEGETABLE GARDEN NW 0.90 1448. F.4E-06 7.4E-04 6.5E-06 2.3E-08 G vfGETABLE GARDEN NNW 3.40 5472. 5.9E-OF 5.FE-OF 4.6E-07 9.6E-10 G RESIDENCES N 0.80 1287. 1.0E-05 1.0E-05 8.9E-06 2.4E-08 G RESIDENCE 5 NME 0.80 128F. 9.1E-06 9.0E-06 8.1E-06 2.0E-08 G RESIDENCES NE 0.90 1448. 4.1E-06 6.0E-06 5.4E-06 1.2E-08 G RESIDENCES ENE 0.90 1448. 4.5E-04 6.4E-04 5.FE-06 1.1E-08 G RESIDENCES E 2.60 4184. 5.2E-07 5.0E-OF 4.2E-07 6.8E-10 G RESIDENCES ESE 3.40 5472. 3.0E-0F 2.9E-OF 2.4E-OF 3.9E-10 G RESIDENCES SE 3.90 6276. 2.3E-07 2.2E-0F 1.FE-07 3.8E-10 G RESIDENCES N 1.30 2092. 1.3E-06 1. 2 E -0 6 1.1E-06 3.FE-09 G RESIDENCES WNW 0.90 1448. 5.5E-06 5.4E-04 4.8E-06 2.0E-08 G RESIDENCES NW 0.90 1448. F.4E-04 F.4E-06 4.5E-06 2.3E-08 G RESIDENCES NNM 2.00 3219. 1.6E-04 1.5E-06 1.3E-06 3.3E-09 G SITE SOUNDARY N 0.80 1287. l.0E-05 1.0E-05 8.9E-06 2.4E-08 O SITE SOUNDARY NME 0.60 966, 1.6E-05 1.6E-05 1.4E-05 3.4E-08 4
C SITE SOUNDARY WE 0.60 966 l.4E-05 1.4E-05 1.3E-05 2.8E-08
] C SITg amammy gNE 0.60 966 l.5E-05 1.5E-05 1.4E-05 - 2.5E-08 C SITE BOUNDARY E 0.80 1287. 6.6E-06 6.6E-06 5.9E-06 1.3E-08 C SITE BOUNDARY ESE 0.60 966. 1.lt-05 1.lt-05 9.8E-06 2.3E-08 4 C SITE ROUNDARY SE 0.60 966. 1.0E-05 1.0E-05 9.3E-06 3.lE-08
, C SITE SOUNDARY SSE 0.80 1287. 6.lt-06 6.0E-06 5.4E-06 2.4E-08 C SITE 30UNDARY S 1.60 2575. 8.6E-07 8.5E-07 7.3E-07 2.7E-09 C SITE SOUNDARY SSW 3.10 4989. 2.9E-07 2.8E-07 2.2E-07 7.9E-10 C SITE SOUNDARY SW 3.40 5472. 3.2E-07 3. l E-07 2.5E-07 9.lt-10 C SITE BOUNDARY WSW 3.50 2414. l.6E-06 8.6E-06 8.4E-06 4.9E-09 C SITE SOUNDARY W l.00 1609. 2.3E-06 2.2E-06 2.0E-06 7.3E-09 C SITE BOUNDARY WWW 0.80 1287. 7.3E-06 7.2E-06 6.4E-06 2.7E-08 C SITE SOUNDARY NW 0.80 1287. 9.9E-06 9.8E-06 8.8E-06 3.2E-08 C SITE SOUNDARY NNW 0.90 1448. 9.lE-06 9.0E-06 8.0E-06 2.4E-08 IIP-1-230, Rev. 4 45 Attachment 10.1 (1 of I)
Tchle 2
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Type Location Analysis Frequency Volume TLD A-2, B-1, C-1, D-2, E-1, TLD* Quarterly N/A F-2,_G-2, N-2, J-2, K-1, L-1, M-1, N-1, P-1, Q-1,
. R-1, A-5, B-4, D-5, E-5, F-4, G-4, H-6, P-6, Q-5, R-6, F-9, G-9, E-15, J-15, E-30 Radiciodine and APP-1, APQ-1, APG-1, Gross beta, I-131 Weekly 3 285m /wk h
Particulates APC-1 APE-30 isotopic Quarterly composite 3700 m3 /qtr Ground Water GWJ-1 y isotopic, H-3 Quarterly 4 liters Drinking Water
- DWG-2, DWE-5 , DWP-7 H-3 Quarterly composite Homogeneous Gross beta, y isotopic Monthly composite 4 liters 1-1318 Semi-monthly composite d
Surface Water
- SWG-2, SWE-5 , SWP-7 H-3 Quarterly composite Homogeneous y isotopic Monthly composite 4 liters Shoreline Sediment SHWE-3 y isotopic Semi-annually 2 kilograms Milk MKE-4, MKQ-5, MKQ-50 y isotopic, I-131 Semi-monthly / monthly 4 liters v3 Fish FH-1, FN-2 y isotopic In season or . 500 grams semi-annually * .W Food Products FPP-1 y isotopic At harvest time 3 500 grams %:'
M Broad Leaf -BLQ-1, BLB-1, BLH-10 y isotopic, I-131 Monthly 500 grams When milk samples d not collected d
HP-1-230, Revision 2 Attachment 10.2 (1 of 2)
Tchle 2 (Ccetinued)
- a. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. A TLD is considered one phosphor, two or more phosphors in a packet are considered two or more dosimeters. Geographical limitations affect siting of .
dosimeters.
- b. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more af ter
. sampling to allow for radon and thoroa daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopes analysis shall be performed on the individual samples. Gamme isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility,
- c. Drinking Water and Surface Water samples are identical samples.
- d. The downstream sample is beyond the mixing zone.
- e. A composite sample will contain aliquots of sample taken proportional to the quantity of flowing liquid that results in a specimen ~ representative of the liquid flaw.
- f. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
3 This analysis will be performed when the dose calculated for the consumption of water is greater than 1 mrem per year as calculated for maximum organ and age group as per the ODCM (see section 8.6).
- h. Milk will be en11ected semimonthly when animals are on pasture, monthly otherwise. If milk sampling is not performed, broad leafy vegetation will be sampled.
- i. Striped mullet, gizzard shad, freshwater drum, and catfish will tur collected. If they are not available, substitute species will be collected and identified in reporting,
- j. One sample of each principal class of food products will be sampled in an area irrigated by water in which plant wastes have been inadvertently. discharged (see section 8.5 of this procedure). If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvesting occurs continuous-ly, sampling shall be monthly. Tuberous and root products will be sampled when available.
IIP-1-230, Revision 4 47 Attachment 10.2 (2 of 2)
TABLE 3 SAMPLE LOCATION TABLE LOCATION LOCATIGH MILES FRON SECT 0R HUMBER DESCRIPTION PLANT DIRECTICH DIRECT RADIATION (TLD)
A-2 ( Eastbank ) On fence enclosure 1.1 N surrounding water tower west of Little Gypsy opposite Etienne St.
Access from River Road (LA 620).
The TLD's are located on the (S)
Pence opposite the entrance gate to the water tower.
B-1 (Eastbank , On fence enclosing the 0.8 HHE transmission tower 0.3 miles west (up-river) frem Little Gypsy.
Access from Rivs.- Road ( LA 620 ).
TLD's are located et SW corner of fence enclosure.
C-1 ( Eastbank ) On fence eaclosing the 0.8 NE Little Gypsy Cooling Water Intake.
Access is from River Road (LA 629) across from Little Gypsy Power Station entrance. TLD's are on the south side (inside) of the Cooling Water Intake fence enclosure, directly opposite the entrance gate.
D-2 ( Eastbank ) Located at USGS Witness f.1 ENE Post Survey Marker approximately 0.3 miles east of Little Gypsy Power Station. Access from River Road (LA 628) near the west end cf the Bonne Carre Spillway. TLD's are on the back of the Survey Marker Sign (located on levee).
E-1 ( Westbank ) Located on utility pole 0.2 E along River Road (LA 10) approxi-mately 0.3 miles east of Waterford 3 plant entrance. Access from LA
- 10. TLD's are on the third utility pole east of the construction entrance road.
HP-1-230, Revision 4 48 Attachment 10.3 ( 1 of 9) e Lm.
Ttblo 3 (continued)
LOCATIGH LOCATIGH MILES FRON SECT 0F HUMBER DESCRIPTION PLANT DIRECT 0rd F-2 ( Westb ank ) Located on fence 1.1 E5E enclosure surrounoing the LPtL substation on LA 3142. Access from LA 3142 approximately 0.2 miles south of LA 18. TLD's are on the southeast corner of the fence enclosure.
C-2 ( Westb-ank ) Located on utility pole 1.2 SE on East side of LA 3142 near Witco entrance gate (Hext to Union Carbide Star Plant Gate 3). Access from
- LA 3142 approximately 0.2 miles north of railroad overpass.
H-2 (Westbank) Located on fence enclosure 1.2 $$E to shell road off of LA 3142. Access from LA 3142 south of railroad overpass on east side of LA 3142. TLD's are on the south side of the gate for shell road. ( Just south of Texaco pipeline station)
J-2 ( Westb ank ) Located on northeast 1.3 $
corner of fence enclosing Tex.aco valve station south of LA 3127.
Access from LA 3127, approximately 0.6 miles west of LA 3127/3142 intersection.
K-1 ( Westbank ) Located behind " Private 1.0 $$U Road" sign at Gate 8 entrance off 4
of LA 3127. Access from LA 3127, approximately 1.3 miles west of LA 3127/3142 intersection. (Gate 8 is the access to the Waterford 3 switchyard station)
L-1 (Westbank) located behind " Private 1.0 SW Road" sign at LP&L Gate 9 entrance off of LA 3127, approximately 1.6
, miles west of LA 3127/3142 inter-section. (Gate 9 is an access road for Waterford 3)
HP-1-230, Revision 4 49 Attachment 10.3 (2 of 9.,
Tcble 3 (continusd)
LOCATION LOCATION MILES FROM .iEC70R HUMBER DESCRIPTION PLANT DIRECTION N-1 (Westbank) Located on south gate 0.7 Wsia into the Waterford 1 and 2 fuel oil storage tank enclosure, Access is either thru LP&L Gate 8, Gate 9 off of LA 3127, the shell
. access road from LA 18 between Waterford 3, or thru the Waterford i and 2 access road.
H-1 -
( Westbank ) Located behind the "No 0.9 W Trespassing" sign off on Short Street, in Killona, just south of the entrance to Killona Elementary School.
P-1 <Westbank) Located behind "No 0.8 WHW Trespassing" sign on Short Street, in Killona, approximately 0.1 miles south of air sample station.
Q-1 (Westbank) Located on fence 0.9 HW enclosing air sample station approximately 0.5 miles west of Waterford I and 2 on River Road (LA 16).
R-1 <Westbank> Located on fence 0.5 Nhy enclosure for Waterford I and 2 Cooling Water Intake Structure.
Access is from River Road (LA 18) opposite W,-terford 1 and 2.
TLD's are on the southwest corner of fence.
A-5 ( Eastbank ) Located on utility 4.5 ri pole just east of the Shady Hook Trailer Park on Hwy 61 in La Place.
TLD's are on second utility pole east of trailer park on north side of Hwy 61 (eastern and of La Place).
HP-1-230, Revision 4 50 Attachment 10.3 < 3 of 9) o ___--___-____________________-_____)
.. _ _.- ~_ - - _._- . _- -
. 1 Table 3 < continued) -
LOCATION LOCATION MILES FROM SECTOR f HUMBER DESCRIPTICH PLANT DIRECTION j B-4 ( Eastbank ) Located on utility pole 3.8 HNE just east of shell access road to j South Central Bell transmission j tower on south side of Hwy 61. i l Transmission tower is just east of >
l ' Weigh Station at St. John /St. Charles :
Parish line. TLD's are on first utility pole east of access road.
i h
D-5 ( Eastbank ) Located on fence gate 4.2 ENE on shall access road to Big 3 Chemical Plant. Shell access road j is approximately 0.1 miles west of ,
Hwy 61/48 intersection (at black ;
and yellow gate). TLD's are on fence gate 0.1 miles north on l shall access road from Hwy 61. j 5 E-5 ( Eastbank ) Located on the Horco 4.2 E l Substation fence enclosure.
1 Access from River Road '(LA 48) ;
onto Wesco St. (adjacent to Horco i Shell Chemical Plant), take Wesco i St. to the dead end. TLD's are located on sixth fence post south t of the north substation gate. . i F-4 ( Westbank ) Located on utility pole 3.5 ESE :
behind blonde brick house on Aquarius SL. in Hahnville. Access from River Road (LA 18) and turn I onto Oak St. Follow Oak St. to- '
Hickory St.,' turn right on Hickory St. and follow to Aquarius St. and turn left. Blonde brick house is second -house on right (west) side :
of Aquarius St. heading south.
, G-4 ( Westbank ) Located on railroad sign 3.2 SE I
j northwest side of LA 3160/ railroad track intersection. Access from either LA 3127 or River Road (LA 10) '
onto LA 3160. ,
{
HP-t-230, Revision 4 51 Attachment 10,3 (4 of 9)
- r e-__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . - _ _ _ _ _ _ . _ . . _ _ . - _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . . _
Tablo 3 (continued)
LOCATIGH LOCATIGH NILES FDON 3ECT0F HUMBER DESCRIPTION PLANT DIREC TICH H-6 ( Westbank ) Located on a construction 5.7 SSE sign on the southuest side of the second canal bridge east of LA 3160 along LA 3127.
P-6 (Westbank) Located on utility pole 5.5 WNW at southwest corner of LA 640/
railroad track intersection. !
Utility pole is just west of LA 640 and east of radio transmission tower. !
1 Q-5 < Westbank ) Located on fence post 5.0 HW surrounding (green) river marker on leves just east of Edgard.
Fence post is located along River Road (LA 18) across from the Webre's house.
R-6 ( Eastbank ) Located on fence 5.3 NHW enclosing LPtL Laydown Yard on LA 3223 in La Place. Access from Hwy 61 onto Elm St. <LA 3223),
take Elm St. to the northeast corner of LA 3223/ railroad inter-section. TLD's are located on I the southeast corner of fence enclosure.
F-9 ( Eastbank ) Located on ente.ance 8.2 ESE gate to Destrehan Substation.
I Access f rom River Road (LA 48),
approximate 0.3 miles east of Luling-Destrehan Ferry, onto Destrehan Road (west of Bunge Corp. Grain Elevator), and proceed to substation gate.
C-9 ( Westbank ) Located on back fence 8.1 SE of LPAL District Office in Luling.
Access.via Ellington St. from ,
either River Road (LA 18); - or Second or Third St. from Paul Mallard Rd. (LA 52) to Ellington St.
HP-1-230, Revision 4 52 Attachment 10.3 (5 of 9)
Tcbic 3 < continued) l LOCATION LOCATION MILES FRON SECT 0F HUMBER DESCRIPTION PLANT DIRECTICH E-15 ( Eastbank ) Located on Kenner 11.8 E Substation fence enclosure.
Access from either River Road (LA 48) or Hwy 61, turn onto Alliance Ave. TLD's are located on the north side of the fence enclosure, near a light pole.
J (Westbank) Located on fence 12.0 $
enclosure surrounding LP&L switchyard at LA 631/ Hwy 90 intersection in Des Allemands.
TLD's are on the northwest corner of Pence. Access from LA 631 via shell road.
E-30* (Westbank) Located on fence at 27.0 E LP&L General Office on Delaronde St. in Algiers. TLD's are on the fence, facing the Mississippi River, in the passageway to the transformer shop.
Airborne ,
APP-1 <Westbank) Located in soybean 0.8 tvH4 field at northwest corner of ;
Short St. in Killona.
APQ-1 (Westbank) Located at northwest 0.8 H4 corner of soybean field on east side of Killona. Access from River Road (LA 18) approximately 0.6 wiles east of LA 18/3141 intersection. ,
APG-1 < Westbank ) Located at the north 0.5 SE side of the Secondary Metrology Tower.
HP-1-230, Revision 4 53 Attachment 10.3 (6 of 9) 1
~
Table 3 (continued)
LOCATION LOCATI0H h1LES FP.ON SECT 0A HUMBER DESCRIPTION PLANT DIRECTICr4 4PC-1 ( Eastbank ) Located inside the 0.8 HE Little Gypsy Cooling Water Int-ska ,
Structure fence enclosure. l APE-30* ( Westbank ) Located on the roof of 27.0 E the LP&L General Office building on Delarende St. in Algiers. ,
Food Products FPP-1 (Westbank) Located in soybean 0.8 tr4u field on eastern edge of Killona, between air sample stations APP-1 and APQ-1.
i Broad Leaf BLQ-1 <Westbank) Located between LA IS 0.8 HW and soybean field on eastern edge I Killona, near air sample station ,'
APQ-1.
r BLB-1 ( Eastbank ) Located at wooded . area 0.8 HHE t at the southwestern corner of the ,
LP&L Little Gypsv plant along River Road.
BLH-10+ <Westbank) Loacted under overhead 9.5 SSE transmission lines along LA 633.
HP-1-230, Revision 4 54 4ttachment 10.3 (7 of 9 )
Tabic 3 (continued)
LOCATICH LOCATION MILES FPON S EC T0 F.
HUMBER DESCRIPTION PLANT DIRECTION Ingestion Milk HKE-4 ( Westbank ) Located .8 miles west 4.0 E of the Time Saver in Hahnville off of River Road.
NKQ-5 < Westbank ) Located at the Webre's 5.0 Hu house, just across LA 18 from river marker, at the eastern end of Edgard.
NKQ-50* ( Eastbank ) Located at the LSU 52 HW Dairy in Baton Rouge.
Fish FH-t* Upstream of the plant intake structure.
FH-2 Downstream of the plant intake structure.
Woterborne GWJ-1 ( Westbank ) Located at 40 Arpent 0.3 $
Canal south of the plant. Access from LA 3127 through LP&L Cate 8.
The canal is northwest of the shell access road / railroad track inter-
.. section.
HP-t-230, Revision 4 55 Attachment 10.3 (G of 9)
Teble 3 (continued)
LOCATIGH LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLANT DIcECTION DMG-2 (Westbank) Located at the Union 2.0 E:iE SWG-2 Carbide drinking water canal.
Access from LA 3t42 through Gate 29.
SHWE-3 ( Westbank ) Located at the Foot 3.0 E Ferry Landing off of LA 18 in Taft.
DWE-5 ( Eastbank ) Located at the 4.5 E SWE-5 St. Charles Parish Waterworks off of River Road (LA 48) near New Sarpy, DWP-7+ <Westbank) Located at the St. 6.5 NU SWP-7 John Parish Waterworks off of LA 10 in Edgard.
- DEHOTES CONTROL LOCATIONS i
?
HP-1-230, Revision 4 56 Attachment 10.3 (9 of 9)
Table 4 SECTOR AND ZONE DESIGNATORS FOR RADIOLOGICAL SAMPLING AND HONITORING POINTS SECTOR NOMENCLATURE ZONE NOMENCLATURE CENTERLINE OF SECTOR IN DEGREES TRUE NORTH 22 \* HILES FROM FROM FACILITY SECTOR FACILITY ZONE O & 360 *A N 0-1 1 225 B NNE l-2 2 45 C NE 2-3 3 67h D ENE 3-4 4 '
90 E E 4-5 5 112 F ESE 5-6 6 135 G SE 6-7 7 157h H or SSE 7-8 8 180 J S 8-9 9 202\ K SSW 9-10 10 225 L SW 10-15 15 247\ M WSW 15-20 20 270 N W 20-25 25 2925 P WNW l 25-30 30 315 . Q NW 35-40 40 3374 R NNW l 40-45 45 45-50 50 AREA SEGMENT - An area is identified by a Sector and Zone designator. Thus, area N-1 is that area which lies between 348 3/4 and lik degrees true north from the facility out to a radius of 1 mile. Area G-4 would be that area between 123 3/4 to 146 k degrees and the 3- and 4-mile arcs from the facility. For Airborne, Ingestion (milk), and Food Products pathways, the sector designator will be preceded by acronyms AP, MK, and FP, respectively.
- The letters I and 0 have been omitted from these sector designators so as to eliminate possible confusion between letters and numbers.
IIP-1-230, Revision 2 57 Attachment 10.4 (I of 1)
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- y,*f,';d
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- ^'a','e';,1;O WITHIN 50 MILES OF WATERFORD 3 3 60
FIGURE 4 LIQUID WASTE MANECEMENT SYSTEM EFFLUENT SOURCES AND RELEASE PATHWAYS AND POINTS SOURCES S YS1 E M S l #IlI AfD A
1
- wies 1C IANit$ l CVCS Cl2M 1AMet A lb B l CONDE I6t R CCS SuRCE TANK CO I A Oil (i E $ *JL M I4 3 CONC I OR e PtmePS OW M SW EM ION EXCitANGERS TANWS AS MISC StadPS l FILIER l PACit AGE S A AND e A AND 9 C AND D A AND 5 CONIAltleafMI SuesPS h R AD4 AIM)N
g= H s'aal=a l+ laE 05" .
l CHE3 451E g SPENT FUEL STORAGE WASIE %
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LAIM'IT SUMPS j j l CONTAestNATED SDluS I I
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1ANKS
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COOLING IEAI , WEI COOLING TOwtR A Apg e
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- t llP-1-230. Rev.4 61 At taciunen t 10.8 (1 of I)
e FIGURE 4 (CONT.)
LIQUID WASTE MANAGEMENT- SYSTEM EFFLUENT SOURCES AND RELEASE PATHWAYS AND POINTS SOURCES N NI$is IL* SINE BLEDING FLOOR ORAINS AND A l lNDU51 RIAL wA5it SAAAPS ANK l
. uaMunt vAtvt l AU1004AllC INDU$iRIAL SUteP PUMPS R AOR AllON ISOLATION VALVt$
WA$it 4 A Ape s % ,N l qgli GrM sue 4P Wo i l
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_I 111'-I-230, Rev.4 62 A t t aclanent 10.8 (2 of 2)
FIGURE 5 GASEOUS EFFLUENT SOUMESs G4SEOUS WASTE MANAGEMENT SYSTEMS EFFLUENT SOURCES AND EXHAUST RELEASE POINTS SOURCES SYSTiftS BtLLASE tolNf5 O
LMt$ CAS 14 CAY PRESEUkK kECUlATOR AUTO-ISutAttoN VAX.WE CAS SURCE NEADER
- I TANES: b!ASN TAME. "
Vdl.14NE CT~L TANE. ggg WAST 4, CAS CAS D&' CAY RADIATION soalC ACID (DNTbS. % -m FILTER % 44N W ESsnas -h TANKS. A.g & M EITOM -, g gyggg 733,g qukNC2 TAME REAC1Dit 'I A AND 3 AND C PBN-IRE-0648 g N . VENT N W LR 4 b WM U H M g 4A)UIP. DuAIN EX)UIP 1 Supy + DRAIN Sutt3 g i
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" W o E010Yd Nol103Wa!03 HP-1-230, Revision 4 64 Attachment 10.10 (1 of 1)
_-. _ _ _ _ _ _ ~ _ _ _ .. ,.- . _ . ~ - - . . . _ . _ . . - - - . .
TABLE 5
_ SITE RELATED LIQUID DOSE FACTORS A;, = ( 3. 78E+ 05 + 2.39E+06BF; )DCFi r (mrem /hr per uCi/ml) 2.)
UJ DCFf < mrem /pCi> At ELEMENT BFj GI LLI LIVER GI LLI LIVER t
Cr-51 2.0E+02 6.69E-07 --
3.20E+02 --
Nn-54 4.0E+02 1.40E_05 4.57E-06 1.34E+04 4.37E+03 Mn-56 4.0E+02 3.67E_06 1.15E-07 3.51E+03 1.20E+02 Fe-55 1.0E+02 1.09E-06 1.90E-06 2.61E+02 4.55E+02 Fe-59 1.0E+02 3.40E-05 1.02E-05 8.14E+03 2.44E+03 Co-58 5.0E+01 1.51E-05 7.45E-07 1.81E+03 8.93E+01 Co-60 5.0E+01 4.02E-05 2.14E-06 4.82E+03 2.57E+02 Ni-63 1.0E+02 1.38E-06 9.01E-06 4.50E+02 2.16E+03 Ni-65 1.0E+02 1.74E-06 6.86E-08 4.17E+02 1.64E+01 Cu-64 5.0E+01 7.10E-06 8.33E-08 8.51E+02 9.99E 00 4 Zn-65 2.0E+03 9.70E-06 1.54E-05 4.64E+04 7.36E+04 1 Sr-89 3.0E+01 4.94E-05 --
3.56E+03 --
Sr-90 3.0E+01 2.19E-04 --
1.58E+04 --
Y-90 2,5E+01 1.02E-04 --
6.13E+03 --
2r-95 3.3E 00 3.09E-05 9.75E-09 2.55E+02 8.06E-02 Zr-97 3.3E 00 1.05E-04 3.39E-10 0.32E+03 2.80E-03 Hb-95 3.0E+04 2.10E-05 3.46E-09 1.51E+06 2.48E+03 I-131 1.5E+01 1.57E-06 5.95E-06 5.69E+0! 2.16E+02 Cs-134 2.0E+03 2.59E-06 1.48E-04 1.24E+04 7.07E+05 Cs-137 2.0E+03 2.11E-06 1.09E-04 1.01E+04 5.21E+05 I
- 1. Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1 , 1 9 7 .' .
- 2. Extracted from Table E-11 of Regulatory Guide 1.109, Revision 1,1977, r
r HP-1-230, Revision 4' . 65 Attachment 10.11 (1 of 1) .
e 9
s _ - , -- - , - - w . - - -
TABLE 6 BIGACCLTJLATION FACTOR FOR FRESHWATER FISH AND INVERTEBRATEl (pCi/Kg per pC1/ liter)
FRESHWATER ELEMENT FISH INVERTEBRATE r
H 9.0E-01 9.0E-01 '
?
C 4.6E 03 9.1E 03 Na 1.0E 02 2.0E 02 ,
r P 1.0E 05 2.0E 04 Cr 2.0E 02 2.0E 03 :
Mn 4.0E 02 9.0E 04 ;
Fe 1.0E 02 3.2E 03 i Co 5.0E 01 2.0E 02 ,
Ni 1.0E 02 1.0E 02 !
+
Cu 5.0E 01 4.0E 02 I
Zn 2.0E 03 1.0E 04 Br 4.2E 02 3.3E 02 j Rb 2.0E 03 1.0E 03 Sr 3.0E 01 1.0E 02 ,
t Y 2.5E 01 1.0E 03 Zr 3.3E 00 6.7E 00 i
l l
l i
- 1. Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1, 1977, HP-1-230, Revision 4 66 Attachment 10.12 (1 of 5) -
i i
TABLE 6 l BI0 ACCUMULATION FACTOR FOR FRESHWATER l l
FISH AND INVERTEBRATE f (pci/Kg per pCi/ liter) f I
FRESHWATER ELEMENT FISH INVERTEBRATE (
i Nb 3.0E-04 1.0E-02 L i
Mo 1.0E 01 1.0E 01 f Tc 1.5E 01 5.0E 00 Ru 1.0E 01 3.0E 02
- i Rh 1.0E 01 3.0E 02 Te ' 4.0E 02 6.1E 03 I 1.5E 01 5.0E 00 Cs 2.0E 03 1.0E 03' Ba 4.0E 00 2.0E 02 La 2.5E 01 1.0E 03 Ce 1.0E 00 1.0E 03 ,
Pr 2.5E 01- 1.0E 03 2.5E 01 Nd 1.0E 03 ii l W 1.2E 03 1.0E 01 j Np 1.0E 01 4.0E 02 I
1 I
- 1. Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1, 1977. !
l t i
~
HP-1-230, Revision 4 67 Attachment 10.12 (2 of 5 ) -
f - . . _ _ , - - ._, .
i l
1 i
TABLE 6 i
i INGE5ftc4 005E FACTORS Fca AQUtts !
, t**EM PE4 *CJ INGE5fE01 f
NUCL!tE 80NE LIVER f.ACCY THYR 0!D KIONEY LUNC GI-LL!
H 3 40 DATA 1.0$E-01 1.03 E-0 7 i
C 14 1.0Si-07 1.0SE-07 1.0SE-07 1.05E-07 2.84E-06 S.68E-07 5.4 8 E -0 7 S.6 8E-0 7 S.68E-07 5.68F-07 S.68E-07 MA 24 1.70E-06 1.70F-06 1. 70 E -0 6 1.70E-06 1.70E-06 1.70F-04 1.70E-06 j 8 32 1.93E-04 1.20f-CS 7.4eE-os 40 UATA NC CATA NO DATA 2.17 E -O S i
CR S1 40 DATA NO CATA 2. 4cE -0 9 S.86E-10 i
MN $4 1.S1E-09 3.53E-09 6.69E-07 NO UATA 4.575-06 8. 72 E-0 7 NO DATA 1.J6E-06 NO DATA 1.60E-05 i i.
NN S6 NO DATA 1.1SC-C7 2.045-04 NO DATA 1.46E-07 No DATA 3.67F-06 rt SS 2.75E-06 1.90F-04 4.4JC-07 NO DATA NO DATA 1.06E-06 1.09E-06 j
FE $9 4.34E-06 1.02E-0S 3.9tE-06 NO DATA 40 DATA 2.8SE-06 3.40E-05 !
CO $8 NO DATA 7.4Si-07 1.47E-06 NO DATA NO DATA CO 60 40 DATA 2.14F-04 NO DATA 1.51E-0S ,
- 4. 72 C-0 6 NO DATA NO DATA NO DATA 4.02E-05 NI 43 1.30E-C4 9.01E-04 4. 3 6 E -0 4 NO DATA NO DATA 1
NO CATA 1.88E-04 L t
NI 64 S.28E-07 6.84E-08 1.13 E-0 8 NO DATA NO DATA 40 DATA Cu 64 NO DATA '8.33E-08 1.74E-06 !
2M 61 3.9t!-08 NO DATA 2.10E-07 40 DATA 7.10E-C6 4.84E-04 1.246-OS e. Set -0 6 NO DATA 1.03E-05 NO CATA 9.70F-06 1
2M 69 1.03E-08 1.97E-08 1.37E-09 NO 0474 1.28E-03 NO DATA 2.96E-09 et 83 10 04T4 NO OA74 4.02E-08 NO DA*A No cafa BR 84 40 DATA NO DAT A ,
NO DATA S.796-08 S. 21 E-0 8 No DATA NO D A TA NO DATA 4.09E-13 l
sa SS 40 CATA NO DATA 2.14 E -0 9 40 DATA NO DATA NO DATA LT E-26 48 86 40 DATA 2.11E-05 9. 8 3 E -0 6 NO DATA . {
NO DATA NO DATA 4.16E-06 '
RS 88 NO DATA 6.CSE-08 3. 2 t E-0 8 N0 CATA NO DATA NO DATA 8.36E-19 ;
as 89 40 DATA 4.01E-08 2. 82 C-0 8 NO DATA NO DATA No DATA 2.33E-21 54'89 3.08E-04 N0 DATA 8. 84 E-0 6 30 DATA NO DATA No DATA i Sa 90 7.58E-03 40 DATA 4.94E-OS
- 1. 86E-0 3 NO DATA 40 DATA NO DATA 2.19E-04
?
I SR 98 S.67E-06 NO DATA 2.27E-17 40 DATA NO DATA
.54 92 40 DATA 2.70E-05 2.15E-06 10 DATA 9.30E-08 NO DATA NO DATA 40 DATA 4.26E-OS Y 90 9.62E-09 NO DATA 2.58E-10 40 DATA N0 DATA NO DATA 1.02E-04 i
. .~.~.. _ - . . . . _ . . . . _ - -
Y 9tm 9 09E-11 NO DATA 3.52E-12 MO DATA NO DATA NO DATA '2.67E-to Y 91 1.41E-07 40 DATA 3. 7 7 E-0 9 NO DATA NO DATA Y 92 8.4SE-10 NO CATA NO DATA 7.76E-05 i 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 I
I i
i i !
f i
HP-1-230, Rev. 4~~ 68 Attachment 10.12 (3 of 5) i t
l l
l TA3LE 6 (continued) l I
I INGEsrION 00$E FACT 0*5 FCm acutis (M4EN Pht PCI INCESTEDI [
t EtDNEY LUNG GI-LLI !
NUCL10E BONE LivEt T.600Y THv901C NO DATA s.50E-05 f Y 95 2.68E-C1 NO DATA 7.40E-11 NO DATA NO DATA ZR 95 3.04E-08 1.75E-09 6. 4 0 E-0 9 No DATA 1.53E-08 NO DATA 3.09E-OS !
ZA 97 1.64E-09 3.39E-10 1.SSE-10 NO DATA S.12E-10 NO DATA 1.CSE-04 l N4 95 6.22E-09 3.*6E-09 1. 86E-0 9 NO DATA 3.42E-09 No DATA 2.10E-05 i MO 99 NO DATA 4.31E-06 a.20C-o f NO CATA 9.76t-06 NO DATA 9.99E-06 :
TC 99m 2.47E-10 6.98E-10 8.89E-U9 NO DATA 1.06E-08 3.42E-10 4.13E-07 i TC101 2.S4E-10 3.66E-10 3. 5 9 E -0 9 NO DATA 6.59E-09 1 87C-10 1.10E-21 aul03 1 5SE-07 NO DATA 7. 9 7 E -0 4 NO CATA 7.06E-07 NO DATA 2.16E-05 tul0S 1.54E-08 Mu OATA 6. 08 E -01 40 DATA 1 99E-07 NO DATA 9.42E-04 autot 2.7SE-04 NO DATA 3. 4 8 E -0 7 NO DATA S.11E-06 NO DATA 1.7 5 E-04 AG110m 1.40E-07 1.64E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-OS TE125m 2.6SE-04 9.71E-07 3. 51C-0 7 8.068-07 1.09t-05 40 DATA 1.07E-45 TE127= 6.77E-06 2.42C-04 8.2S E-0 7 1.73E-06 2.75E-05 NO DATA 2.2 7E-05 TE127 1.10 E-0 F 3.95E-08 2.3aE-08 8.15E-08 4.48E-07 NO DATA s.68E-06 TE129p 1.1SE-05 4.298-06 1. 82 E -0 6 3.95E-04 4. 8 0 E -05 NO DATA S.79E-0S TE129 3 14E-04 1.18E-08 7. 6 s E-0 9 2.41E-os 1.32E-07 NO CATA 2.37E-Os TC131m 1.73E-04 5.44C-07 7.C S E-0 7 1 34E-04 8.57E-06 40 DATA 4.40E-05 TE131 1.97E-08 4.23E-09 4.225-09 1 62E-04 s.63E-04 40 DATA 2.79E-09 TE132 2.52E-06 1 43E-06 1. S J E -0 4 1.40E-06 1. 5 7E-05 40 DATA 7.71E-05 1 130 7.56E-07 2.21E-06 8. 4 0 E-0 7 1 89E-04 3 48E-06 NO DATA 1 92E-06 I 131 4.16E-06 S.95E-04 3. 41 E-0 6 1.95E-03 1.021-65 NO DATA 1.57E-06 I 132 2.03E-07 S.43F-07 1 90E-0 7 1.90E-05 8.6Sk-07 40 DATA 1.02E-07 1 133 1.42E-04 2.4TE-06 7. 5 3 E-0 7 3.63E-04 4.311-06 NO DATA 2.22E-06 1 134 1.0 6E-07 2.4eE-07 1.03E-47 4.99E-04 4.SSE-07 40 QATA 2.51E-10 1 135 4.43E-07 1.162-04 4.2 SE-0 7 7.4SE-05 1. 46 E -06 NO DATA 1.31E-04 C5134 6.22E-05 1.4aE-04 1. 21 E -0 4 NO DATA 4.794-05 1.59E-OS 2.59E-46 C5136 6.51E-06 2.57E-05 1. s S E -0 5 No DATA 1.43E-OS 1.96E-06 2.92E-c6 C5137 7.97E-05 1.09E-04 7.14 E -0 5 NO DATA 3.70E-OS 1.23E-05 2.11E-06 C5138 S.52E-08 1.c9E-07 S.40E-04 NO DATA S.01E-as 7.91E-09 4.4SE-13 SA139 9.70E-08 4.91E-11 2.844-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 HP-1-230, Rev. 4 69 Attachment 10.12 (4 of 5 )
TABLE 6 (continued) ,
i r
l INGE1710N 005E FAC70R$ FOR A0utr$
teaEM PLR PCI INDESTE01 NuCLICE BONE Ltvtt f.800Y TNya010 RIONEY LUNC GI-LL! !
2.0JC-05 SA140 2.55E-08 1.33E-06 140 DATA n. aft-09 1.46E-08 4.18E-05 AA141 4.11E-os 1.44C-11 1. 5 9 E -0 9 NO DATA 3.31E-11 2.02E-11 2.225-17 94142 2.13E-08 2.196-11 1. 3 6 t -0 9 40 DATA 1.35E-11 1 24E-11 1.00E-26 LA140 2.50L-09 1.262-09 4.3JC-10 NO DATA NO DATA NO DATA 9.25E-05 l' LA142 1 28E-10 5.42!-11 1.45E-11 NO DATA NC 047& NO DATA 4.25E-07 OE141 9.36E-09 6.lsF-09 F.14 E-10 No DATA 2 94E-09 NO QATA 2.42E-05 l CE143 1.45E-09 1.22F-06 1.35E-10 NO DATA 5.37E-10 No DATA 4.56E-05 -
CE144 4.A8E-07 2.04E-07 2. 62 E-0 4 NO DATA 1.21E-07 NO DATA 1. 4 5 E- 04 i PR143 9.2 0 E -09 3.69C-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 '
Pt:44 3.01E-11 1.2SE-11 1.55E-12 MO DATA 7.05E-12 No DATA 4.33E-La N0147 6.29E-09 7.J7E-09 4. 3 5 E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 m.117 1.03E-07 8.61E-08 3.01 E-0 3 NO DATA NO DATA Mn cafa 2.825-05 . ,
_ _ _ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ _ _ _ . . . . . . . . . _ _ _ _ _ i t47239 1.19E-09 1.17C-10 6. 4 S E-1 1 NO DATA 3.65E-10 No cafA '2.40E-05 L
r A
HP-1-230, Rev. 4 70 Attachment 10.12 (5 of 5)
l l
l TABLE 7 00$E FACTOs$ FOR EXPOSURE TO A SEMT-!MFINITE CLCUO OF N0!LE GA!!! f t
Muclide s. ate *( Nt ) s-Skin **f ti) -Air *fMi) ledy ' Ki i Kr-83e 2.88E-04 ---
1.93E-05 7.56E-04 f I
Kr-85e 1.97E-03 1.46E-03 1.23E-03 1.17E-03 [
Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 !
i Kr-87 1.03E-02 9.73E 03 6.17E-03 5.92E-03 i Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 ;
Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 I i.
)
Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 !
Ie-131e 1.11E-03 4.76E-04 1.54E-04 9.15E-05
, Ie-133's 1.48C-03 9.94E-04 3.27E-04 2.51E-04 .
Ie-133 1. 05 E 3.06E-04 3.53E-04 2.94E-04 Ie-135e 7.39E-04 7.11E-04 3.36E-03 3.12E-03 !
Ie-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 f i*
Ie-137 1.27E-02 1.22E-02 1. 51 E -03 1.42E-03 Ie-\38 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 -
9.30E-03 8.84E-03 l I
3 ered-e pC l-p r -
- i eree-e 3 pGl-pr r
2.88E-04 = 2.88 x 10~" ^
t i
I t
I
(
! I l s: h 1
HP-1-230, Rev. 4 71 ' Attachment 10.13 (lof1)
i i
I
\
TABLE 8
)
INMALATION OCSE 84CTORS FC4 CHILD (DFAi ) l
("4EM PE4 PCI INMALE01 +
i NUCLICE BONE Liven T. ACCY Thvuoto stDNEY LuNC Cl-LLI ;
H J NO DATA 3.C4C-17 3. 04 E -01 1.04d-07 1.04C-07 3.04E-07 1.04E-07 C 14 9.70E-06 1.82E-06 1.92E-06 1.42E-04 1.42E-06 1.42E-06 1.82E-06 NA 24 4.3SE-C6 4.JS2-06 4. 3 5 E -0 6 4.35E-on 4.3SE-e6 *.3SE-06 4.3SE-04 P 32 7.04E-04 1.r9E-OS 2. 6 f t -0 5 NO DATA NC CATA No DATA 1.14E-05 CA St No DATA No DATA 4.17E-08 2.J1r-ca 6.576-09 4.59E-06 2.93E-07 MN S4 '40 C A T A 1.165-05 2.57F-Oe NU OATA 2.7tE-06 4.26E-04 6.19F-04
- N $6 NU 04 T A 4.64E-10 0.43E-11 No DATA 4.52E-10 3.SSE-06 1.33E-OS i rt SS 1.2sE-05 6.00E-06 2.1GE-06 No 04f4 40 DATA 3.00E-05 7.75E-07
- E 59 S.39C-06 9.c4E-06 4. 5 t C-0 6 Nu DATA NO DATA 3.*3C-04 1.9tE-OS l CD $4 NO DATA 4.11E-07 8. S S E-0 7 No DATs NC OATA 2.99C-04 9.2 9 E-0 4 l CO 40 NO DATA 3.SSE-06 4 12 E -0 6 No Defa NO DATA 1.91E-03 2.6CE-05 '
NI 63 2.22E-04 1.2SF-05 7.56E-06 40 QATA NO DATA 7.43E-05 1.7tE-06 '
- 41 65 s.csE-!Q 7.99E-11 4.4*E-11 No DATA NC OATA 2.2tE-04 2.2 7E-05 Cu 64 40 DATA S.J9E-to 2.90C-Lo No DATA 1.43E-09 2.59E-06 9.92E-06 2.4 65 1.tSE-05 3.044-05 1. 90 E -0 5 40 DATA 1.91E-0* 2.69E-04 *.41E-04 2 N 61 1. ale-11 2.61E-11 2.4 t C-12 NO DATA 1.58E-tt 3.a*E-07 2.75E-06 (
nt 83 NO DATA NO DATA 1.2 8E-0 7 NO DATA NO DATA A0 DATA LT E-24 i oR 44 NO DATA NU OATA 1. 4 s E-0 7 NO DATA NC'OATA NC CATA L T E-24 ,
_ . _ _ . - _ _ _ . _ _ . . _ _ . _ _ . _ _ _ - i 29 SS NO OATA 40 DATA 6.44E-09 Nn DATA NG DATA NO DATA LT E-24 '
m8 46 NO DATA S.36C-05 1.09E-03 NO CATA NO CATA ko DATA 2.16E-06 l Re 84 NO DATA 1. 5 2E-O F 9.90C-Os NO DATA NO Daft NO DATA 4.66E-09 40 89 NO DATA 9.3)C-00 7. 8 a E -0 4 NO DATA NC DATA NO DATA S.11E-to i 59 39 1.62E-04 NO CATA 4. 6* E -0 6 NO DATA NO DATA S.81C-04 4.52E-05 i Sa 90 2.73E-02 No CATA 1. 74E-0 3 NO DATA NC OATA 3.99C-03 9.2sE-OS t
_.....__________.._________..._______ _ ____ l SR 91 3.2SE-04 NO DATA 1. 2 4 E -0 9 No DATA NO DATA 1.4*E-05 4.708-05 i
$R 92 3 34E-09 NO DATA 1.42E-10 NO DATA N0 DA TA 6.49C-04 6.SSE-05 !
Y to 1.ItE-04 No DATA 2.94F-Os NO DATA NO DATA 7.07E-05 7 2*E-05 i Y. 9tp 1.17E-10 No DATA 4.9 8E-12 NO DATA no CATA 7.60F-07 4.64 E-0 7 $
Y 91 2.47E-04 NO DATA 4. 5 9 E -0 6 No DATA No DATA 7.10E-04 4.97E-05 !
Y 92 S.50E-09 NO DATA 1 5 7 E-10 NO 0474 NO DATA 6.46E-C6 6.46E-05 l
i i
I i
+
l l
EP-1-230, Rev. 4' 72 Attachment 10.14 (1 of 3)
- t. _ - -
i TABLE 8 (Continued) i tanALArtuN OLse FActuas rea CHILO (DFA1 )
("4EN PCR *CI INMALEDI iUCLICE BuME Lryg4 T . d C CY THYR 010 E!DsEY LUNG GI-LL1 Y 15 S.04E-04 40 DATA 1.3st-09 MO Daft NO DAT6 2.01E-05 1.0SE-04 22 95 S.lJE-OS 1.13E-OS 1.00E-OS 40 DATA 1 61t-oS 6.03F-04 1.65C-05 28 97 S.07C-Os 7.J4E-09 4. J 2 E-0 9 NO DATA 1.0SE=CS 1.06E=0S 9.49E=0S 48 9S 6.3SE-06 2.48E-06 1. 7 7 E -0 6 No CATA 2.33E-06 1.66E-04 1.00E-0S
, m0 99 MO DATA 4.66E-04 1.13E-04 NO DATA 1.06E-07 3.66E-OS 1.42E-OS
^
IC 99P 4.81E-13 9.41C-13 1.S6E-11 MO DATA 1 37E-11 7.575-c7 1 30E-06 TC101 2.19E-14 2.30E-14 2.915-13 NO DATA 3.1?E-13 1.DAE-07 4.418-09 2U103 7.SSE-07 No DATA 2.90F-0 7 NO DATA 1.10E-06 1.79E-04 1.21E-05 4
au105 4.13E-10 4U CATA 1.30E-10 an OATA 3.43E-10 4.30E-06 2.69E-05
! aul06 3.44E-OS NO DATA 4.57F-06 40 DATA 4.9FE-05 3.87E-03 1.16E-04 AG110m 4.54E-06 3.08E-06 2. 4 7 E-0 6 Mn DATA S.74L-06 1.4af-03 2.71E-CS I
TE12Sm 1.325-04 6.295-07 2. 47E-0 7 1.202-07 NC QATA 1.29E-04 9.13E-06 TE127m 6.72E-06 2.31E-04 8.1 =E -0 7 1.64E-04 1.721-05 4.00C-04 1.93E-05 TE127 7.49E-10 2. $ 7E- 10 1. 4 S E-10 S.30E-10 1.911-09 2. 71 F-06 1.52E-05 TE12?w S.19E-06 1.4SE-04 8.22E-07 1.7tE-06 1.146-05 4.76E-04 4.9tE-05 i TE129 2.64E-11 9.4SE-12 6.44C-12 1.93E-Il 6.94L-11 7.91E-07 6.49E-06 i TE13tp 3.43E-08 1.60E-08 1.37E-os 2.64E-00 1.08E-07 S.S6E-05 8.325-0S TE131 S.47C-12 2.2st-12 1.7st-12 4.S9k-12 1.59C-11 S.SSE-07 3.60E-07 .
i TE132 1.30E-07 7.34E-08 7 12E-oe S.b4E-08 4.79t-07 1.02E-04 3.72E-05 1 130 2.21E-04 4.4JE-06 2.28E-06 4.99E-04 6.41k-06 40 DATA 1.3st-04 '
I 131 1.30E-05 1.30E-OS 7. 3 7 E-04 4.39E-03 2.136-09 MC DATA 7.64E-07 !
1 132 S.72E-07 1.10E-06 S.0 f E-0 7 S.25E-OS 1.49E-04 =0 QATA 3.6SE-07 1 133 4.44C-04 S.49C-06 2.00 E-0 6 1.04E-03 9 13E-06 20 DATA 1.44E-04 l l t 134 3.17E-07 5.841-07 2.41E -0 7 1.37E-05 8.92E-07 MO DATA 2. Set-07 s t 13S 1.33E-04 2.16E-06 1.12 E -0 6 2.14C-04 3.62E-06 40 DA7A 1.20E-06 i C1134 1. 76E-04 2. 74E-04 6.07E-0$ 40 DATA 4.73E-09 3.27E-05 1.04E-06 :
C3136 1.764-05 4.62E-OS 3.1*E-OS 40 OATA 2.58E-OS 3.93E-04 1.13E-06 l l
C5137 2.4SE-04 2.23E-04 1.47E-OS 40 QATA 7.63E-05 2.stE-OS 9.74E-07 !
C3138 1.71E-07 2.2 7E-07 1.SOE-0 7 NO DATA 1.68E-07 1.84E-08 7.29E-08 j A4139 4.98E-10 2.46F-13 1.4SE-11 40 OATA 2.33E-13 1.56E-06 1. 56E-0 5
.. .. - ~ _ .. _ .- - ... ,
I l l .
i l
l I
I i
a 5
HP-1-230, Rev. 4 73 Attachment 10.14 (2 of 3) f
c TABLE 8 (concinued)
INMALATION OUSE FeCTORS FOR CHILO (DFA1 )
( P R E M, P!4 8CI INHALF03 NUCLIUC SUNE L! E4 f.500Y THya0 0 KIONEY LuNC O!-LLt GA140 2.00E-OS 1 75E-Ce 1. t FC-0 6 NO DATA S.7th-09 '.715-0* 2.75E-05 8A141 S.29E-It 2.15E-t* 1.727-12 NO CATA 7.56d-16 7.89E-07 T.64E-08 8A142 1.35E-it 1.73C-11 7. 3*C-13 NO CATA 7.37E-IS 4.4*C-07 7.61F-10 Lat40 1.74E-07 6.csE-04 2.04E-os 90 DATA NO DATA 6.96E-OS 6.10E-05 LA142 3.SOE-10 1.ttE-10 3.49E-It NO DATA NO CATA 2.3SF-06 2.0SE-05 Cit 41 1.04E-OS S.28E-04 F . 4 3 C -0 7 NO DATA 2.3tE-06 1.67E-06 1.53E-CS CE!*3 9.89E-Ce S. 3 7E-Ce 7.77E-19 NO DATA 2.264-04 3.12E-05 1.4*E-05 CE144 1.83E-03 S.72C-04 9.77E-OS 40 DATA 3.17E-06 3.23C-03 1.0SE-04 74143 4.99E-06 1.30E-04 2.4TE-0T No CATA 8.11t-07 1.17E-04 2.63E-05 Pet 44 1.61E-tt 4.99d-12 0.10E-13 No DATA 2.644-12 4.23E-47 S.32E-ne N0147 2.92E-06 2.36E-04 1. s
- f -0 7 No CATA 1.10E-06 a.47k-0S 2.227-05 w 187 4.41E-09 2.41C-09 1.17 F -0 9 N0'OATA MC CATA 1.11F-OS 2.66E-05 MP239 1.26E-07 9.048-09 6.3SE-19 NO DATA 2.63E-08 1.57E-05 1.73E-OS HP-1-230, Rev. 4 74 Attachment 10.14'(3 of 3)
L
r:
e TA8l.E 9 values of L-lheta-v (Inversa No t er s-59uar s d)
Calculated using open-ferrain Factors Pathsays MILA 604t$
-Sector Distance Pasquill Category -
(Miles) (Heters) 4 1 0 D E F G EN! J.9 1443 4.J3E-06 2.00E-05 SySTE-05 1.17E204 1.71E-04 2.61E-04 3.93t-04 E 3.5 5311 5.231-97 T.70C-07 1.57E-06 5.6TE-06 9.01E-06 1.46E-05 2.35E-05 HP-1-230. Rev.4 75 Attachment 10.15 (1 of 5)
O o
I r
TABIE 9 (014tr.)
velues of L-theta-v l '. (Iowersa Meters-5qwared)
Csiculated Using Open-ferraan Factors Patheart MILE COWS ~
Sector Distance Pasqutil Catboory P (Ni!*s) . (Meters) a 8 0 0 f F G l
E 5.3 5311 5.25E-0T T. TOE-07 1.8FE-06 5.6TE-06 9.0lf-06 1.4of-05 2.35E-05 NW 4.4 7041' 1.44E-0T 3. TOE-07 2.&8E-0T 3.1$E-06 5.18f-06 S.52E-06 1.40t-05 i
I I
i i
r HP-1-230, Rev.4 76 Attachment 10.15 (2 of 5) t
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$ Table 9 (continued) r N. Value s of L-Thata-v 0 (Inverse Maters-Squared) n Calculated using Open-Tarrain Factors Patnway: SITE 33UNDARY y Sectar Distanca Pasquill Category
- (Milas) (Maters) #. B C D E F G H 0.3 1237 7.77E-16 4.13E-05 7.73E-05 1.59E-04 ?.32E-04 3.54E-04 5.4]E-04 NNE 0.6 966 2.015-05 7.94E-05 1.42E-04 2.745-24 4.01E-04 6.21E-04 1.61E-04 ui :) . o 965 2.01E-05 7.94E-35 1.425-04 2.74E-34 4.01E-04 6.215-04 7.61E-04
.ENE J.6 9o0 2. il1 E-0 5 7.74E-05 1.42E-34 2.74E-04 4.01E-04 6.21E-04 9.615-04 E 3.o 12S7 7.7?E-04 4.13E-05 7.765-05 1.59E-34 2.32E-04 3.54E-04 5.40E-04 ESE 0.5 96t 2.01F-05 7.94E-35 1.42E-0, 2.745-04 4.01E-94 6.21E-04 9.61E-04
> SE J.o 763 2.015-05 7.74E-05 1.42E-04 2.74E-04 4. 01 E-0 4 6.21E-04 9.616-04 0 SSE .J.3 12$7 7.77c-06 4.155-05 7.7SE-05 1.59E-04 2.325--04 3.56E-04 3.40E-04 R 5 1.3 2575 1.6SE-05 5.460-36 1.165-05 2.322-05 4.21E-05 6.SoE-05 1.02E-04
[ 35W ' 3.1 4959 5.75E-37 9.375-37 ?.135-06 6.46E-06 1.02E-05 1.44E-05 2.655-05
- g 5d 3.4 3472 5.00E-07 7.13E-07 1.74E-06 5.325-00 S.49E-06 1.33E-05 2.235-05
" WSW 1.5 2414 1.355-00 6.55E-06 1.35E-35 3.29E-05 4.995-05 7.59E-05 1.1LE-04 E; W 1.0 15ul 3.715-30 2.125-05 4.15E-05 $.915-05 1.30E-04 2.90E-04 3.06E-04
- . WNd 0.3 1287 7.77E-05 4.13E-05 7.78E-05 1.59E-04 2.32E-04 3.542-04 5.40E-94 U' Na 9.3 1247 7.77E-90 4.155-05 7.76E-05 1.59E-04 2.32E-04 3.545-04 5. 4 0 5 -J 4 g N4W 0./ 1441 4.J3E-00 2.40E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-94 3 . 9 3 E - 9 '.
O.
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J
TABLE 10 PATHWAY DOSE FACTORS DUE TO RAD 10NUCl.lDES OTHER THAN N0BLE GASES, R 1
EHVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R( I) FOR CASEQU5 DISCHARGES PATHWAY: INHALATION AGE GROUP: IHFANT (1 0F 4)
HUCLIDE ORGAH D 0 S E- FACT 0RS (NREN/YR PER UCI/CU.NETER)
TOTAL 80DY BONE LIVER THYROID KIDHEY LUNG GI-LLI H----3 .647E+03 .000E+00 .647E+03 .647E+03 .647E+03 .647E+03 .647E+03
'CR--Si .992E+02 .000E+00 .000E+00 .575E+02 .132E+02 .128E+05 .357E*03 MH--54 .498E+04 .000E+00 .253E+05 .000E+00 .496E+04 .100E+07 .706Er04 FE--59 .948E+04 .136E+05 .235E+05 .000E+00 .000E+00 .302E+07 .24dE+05 C0--58 .182E+04 .000E+00 .122E+04 .000E+00 .000E+00 .777E+06 .lltE+05 C0--60 .ll8E+05 .000E+00 .802E+04 .000E+00 .000E+00 .451E+07 .'319E+05 ZH--65 .3tlE+05 .193E+05 .626E+05 .000E+00 .325E+05 .647E+06 .514E+05 SR--89 .ll4E+05 .398E+06 .000E+00 .000E+00 .000E+00 .203E+07 .612E uS SR--90 .259E+07 .409E+08 .000E+00 .000E+00 .000E+00 .ll2E+08 .131 E4 0r.
t ZR--95 .203E+05 .Il5E+06 .279E+05- .000E+00 .31tE+05 .l?5E+07 .217E+05 I
I--131 .196E+05 .379E+05 .444E+05 .148E+08 .518E+05 .000E+00 .306E+44 I--133 .560E+04 .132E+05 .192E+05 .356E+07 .224E+05 .000E+00 .216E*04 CS-134 .745E+05 .396E+06 .703E+06 .000E+00 .190E+06 .834E+05 .133E+04 CS-136 .529E+05 .483E+05 .135E+06 .000E+00 .564E+05 .ll8E+05 .143E4 04 CS-137 .455E+05 .549E+06 .612E+06 .000E+00 .172E+06 .713E+05 . 133E+04 BA-140 .290E+04 .560E+05 .560E+02 .000E+00 .134E+02 .160E+07 .384E+05 l CE-141 .199E+04' .277E+05 .167E+05 .000E+00 .525E+04 .517E+06 .216E*05 1
1 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHD A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITI0H llP-1-230, Revision 4 80 Attacliment 10.16 (1 of 19)
TABLE UD (CON'T) .
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i
EHVIRONMENTAL PATHWAY-DOSE C0HVERSIGH FACTORS R(I) FOR GASEQUS DISCHARGES PATHWAY: IHHALATION AGE GROUP: CHILD (2 0F 4)
HUCLIDE 0.R G A N D0SE FACT 0RS (NREN/YR PER UCI/CU. METER)
TOTAL BODY BONE LIVER THYROID KIDHEY LUHG CI-LLI H----3 .ll2E+04 .000E+00 .ll2E+04 .ll2E+04 .ll2E+04 .ll2E+04 .ll2E+04
'CR--51 .154E+03 .000E+00 .000E+00 .855E+02 .243E+02 .170E+05 .108E+04 NH--54 .95tE+04 .000E+00 .429E+05 .000E+00 .100E+05 .158E+07 .229E+05 FE--59 ,167E+05 .207E+05 .334E+05 .000E+00 .000E+00 .127E+07 .707E+05 C0--58 .316E+04 .000E+00 .177E+04 .000E+00 .000E+00 .lllE+07 .344E+05 C0--60' .226E+05 .000E+00 .13tE+05 .000E+00 .000E+00 .707E+07 .962E+05 2H--65 .703E+C5 .426E+05 .ll3E+06 .000E+00 .714E+05 .995E+06 .163E+05 SR--89 .l?2E+05 .599E+06 .000E+00 .000E+00 .000E+00 .216E+07 .167E+06 SR--90 .644E+07 .101E+09 .000E+00 .000E+00 .000E+00 .lllE+08 .343E+06 2R--95 .370E+05 .190E+06 .488E+05 .000E+00 .596E+05 .223E+07 .610E+05 I--131 .273E+05 .48tE+05 .48tE+05 .162E+08 .788E+05 .000E+00 .284E+04 I--133 .770E+04 .166E+05 .203E+05 .385E+07 .338E+05 .000E+00 .548E+04 CS-134- .225E+06 .631E+06 .10lE+07 .000E+00 .330E+06 .12tE+06 .385E+04 CS-136 .ll6E+06 .65tE+05 .171E+06 .000E+00 .955E+05 .145E+05 .418E+04 CS-137 .120E+06 .907E+06 .825E+06 .000E+00 .282E+06 .104E+06 .362E+04 BA-140 .433E404. .740E+05' .648E+02 .000E+00 .2tlE+02 .174E+07 .102E+06 CE-141 .290E+04. .392E+05 .195E+05 .000E+00 .855E+04 .544E+06 .566E+05 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR/ '/0, DEPLETED X/G AND RELATIVE DEPOSITION llP-1-230, Reision 4 81 Attachment 10.16 (2 of 19)
TABLE l0 (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN N0BLE GASES, R 1
ENVIROHNENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY: 1.HHALATIDH ACE GROUP: TEEH (3 0F 4 )
HUCLIDE ORGAH D0SE FACTORS < NREN/YR PER UCI/CU.NETER )
TOTAL BODY BONE LIVER THYROID KIDHEY LUNG GI-LLI H----3 .127E+04 .000E+00 .127E+04 .127E+04 .127E+04 .127E+04 .127E+04 CR--Si .135E+03 ,000E+00 .000E+00 .750E+02 .307E+02 .210E+05 .300E+04 NH--54 .840E+04 .000E+00 .511E+05 .000E+00 .127E+05 .198E+07 .668E+05 FE--59 .343E+05 .159E+05 .370E+05 .000E+00 .000E+00 .tS3E+07 .178E+06 C0--58 .278E+04 .000E+00 .207E+04 .000E+00 .000E+00 .134E+07 .952E+05 C0--60 .198E+05 .000E+00 .tStE+05 .000E+00 .000E+00 .872E+07 .259E+06 2H--65 .624E+05 .386E+05 .134E+06 .000E+00 .864E+05 .324E+07 .466E+05 SR--89 .125E+05- .434E+06 .000E+00 .000E+00 .000E+00 .242E+07 .37tE+06 SR--90 .668E+07 .108E+09 .000E+00 .000E+00 .000E+00 .165E+08 765E+06 2R--95 .315E+05 .146E+06 .458E+05 .000E+00 .674E+05 .269E+07 .149E+06 I--131 .264E+05 .354E+05 .49tE+05 .146E+08 .840E+05 .000E+00 .649E404 I--133 .622E+04 .122E+05 .205E+05 .292E+07 .359E+05 .000E+00 .103E+05 CS-134 .549E+06 .502E+06 .ll3E+07 .000E+00 .375E+06 .146E+06 .976E+04 CS-136 .137E+06 .515E+05 .194E+06 .000E+00 .110E+06 .l?8E+05 .109E+05 CS-137 .3ttE+06 .670E+06 .848E+06 .000E+00 .304E+06 .121E+06 .840E+04 BA-140 .352E+04 .54?E+05 ,670E+02 .000E400 .228E+02 .203E+0? .229E+06 CE-141 .21?E+04 .284E+05 .190E+05 .000E+00 .888E+04 .614E+06 .126E+06 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF l FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITI0H IIP- 1 -2 3's , F:evision 4 82 Attachment 10.16 (3 Of 19)
TABLE 10 (CON'T) ,
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER TilAN NOBLE GASES, R 1
ENVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R( I ) FOR CASEOUS DISCHARGES ,
PATHWAY: IHHALATION ACE GROUP: ADULT (4 0F 4 )
HUCLIDE ~0RGAN D0SE FACT 0RS < HREN/YR PER UCI/CU.NETER )
TOTAL BODY HBONE LIVER THYROID KIDHEY LUNG GI-LLI H----3 .126E+04 .000E+00 .126E+04 .126E+04 .126E+04 .126E+04 .126E+04
'CR--51 .100E+03 .000E+00 .000E+00 .595E+02 .228E+02 .144E+05 .332E+04 NH--54 .630E+04 .000E+00 .396E+05 .000E+00 ,984E4 04 .140E+07 .774E+05 FE--59 .106E+05 .ll8E+05 .278E+05 .000E+00 .000E400 .102E+07 .188E+06 C0--58 .207E+04 .000E+00 .158E+04 .000E+00 .000E+00 .928E+06 .106E+06
. CD--60 .148E+05 .000E+00 .l15E+05 .000E+00 .000E400 .597E+07 .285E+06 2H--65 .466E+05 .324E+05 .103E+06 .000E+00 .690E405 .864E+06 .534E+05 SR--89 .872E+04 ,304E+06 .000E+00 .000E+00 .000E+00 .140E+07 .350E+06 i SR--90 .610E+0? .992E+08 .000E+00 .000E+00 .000E+00 .960E+07 .722E+06 f
2R--95 .233E+05 .107E+06 .344E+05 .000E+00 .542E+05 .177E+07 .150E+06 i I--131 .205E+05 .252E+05 .358E+05 .119E+08 .613E+05 .000E+00 .628E+04 I--133 .452E+04 .864E+04 .148E+05 .215E+07 . 258E+05 .000E+00 .888E+04 CS-134 .728E+06 .373E+06 .848E+06 .000 +00 .287E406 .976E+05 .104E+05
.CS-136 .110E+06 .390E+05 .146E+06 .000E+00' .856E+05 .120E+05 .ll?E+05 CS-137 .420E+06 .478E+06 .62tE+06 .000E+00 .222E+06 .752E+05 .164E+05 l BA-140 .257E+04 .390E+05 .490E+02 .000E+00 .167E402 .327E+07 .218E+06 CE-141 .153E+04 .199E+05 .135E+05 .000E+00 .626E+04 .362E+06 .120E+06 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A YALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION llP-1-230, Revision 4 83 Attachment 10.16 (4 of 19)
TABLE 10 (CON'T)- .
, PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER
. THAN NOBLE GASES, R 1
ENVIRONMENTAL PATHWAY-DOSE CONVERSIGH FACTORS R< !) FOR CASEQUS DISCH4RGES PATHWAY: GROUND-PLAHE DEPOSITI0H AGE GROUP: ALL (l 0F 1)
HUCLIDE ORGAN D0SE FACTORS ( SQ. METE:R-MREM /YR PER L'CI/SEC )
H----3 .000E+00 CR--Si .463E+07 NH--54 .138E+l0 FE--59 .271E+09 C0--58 .376E+09 CO--60 .215E+11 2H--65 .74tE+09 SR--89 .215E+05 SR--90 .000E+00
.2R--95 .243E+09 I--131 .l?2E+08 I--133 .245E+07 CS-134 .477E+10 CS-136 .lSOE+09 CS-137 .103E+ll BA-140 .204E+08 CE-141 .136E+C8 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/O HND RELATIVE DEPOSITION IIP-1-230, Revision 4 84 Attachment 10.16 (5 of 19)
. - . - . _ = - - . . - ,-_-
TABLE 10 -(CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER
- THAN N0BLE GASES, R 1
ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R( I ) F0R GASEOUS DISCHHRGES PATHWAY: COWS MILK (COHTAHIHATED FORAGE) AGE GROUP: INFANT (1 0F 4)
~
HUCLIDE ORCAH D0SE FACTORS (SQ. METER-NREH/YR PER UCI/SEC) total BODY BONE LIVER THYROID KIDHEY LUHG GI-LLI
_______ ________ ________ ________ n_______ ___-____ ________ ________
H----3 .238E+04 .000E+00 .238E+04 .238E+04 . 238E+04 .238E+04 . 238E+04 CR--51 .804E+06 .000E+00 .000E+00 .525E+06 . itSE+06 .102E+07 . 234E+08 HH--54 .442E+08 .000E+00 .195E+09 .000E+00 . 432E+08 .000E+00 . 716E+08 FE--59 .770E+09 .ll2E+10 .196E+10 .000E+00 . 000E+00 .578E+09 . 934E+09
. C0--58 .300E+09 .000E+00 .121E+09 .000E+00 . 000E+00 .000E+00 . 302E+09 CO--60 .104E+10
- 000E+00
. .44tE+09 .000E+00 . 000E+00 .000E+00 . 105E+10 2H--65 .439E+11 .277E+11 .95tE+il .000E+00 . 46tE+11 .000E+00 . 803E+11 SR--89 .180E+10 .628E+ll .000E+00 .000E+00 . 000E+00 .000E+00 . 129E+10 SR--90 .t55E+12 .608E+12 .000E+00 .000E+00 . 000E+00 .000E+00 . 759E+10 2R--95 .587E+04 .340E+05 .828E+04 .000E+00 . 892E+04 .000E+00 . 412E+07 I--131 .14tE+10 .27tE+10 .320E+10 .105E+13 . 373E+10 .000E+00 . 114E+09 I--133 .155E+08 .363E+08 .529E+08 .962E+10 . 700E+08 .000E+00 . 895E+07 CS-134 .340E+ll .181E+12 .337E+12 .000E+00 . 867E+11 .356E+11 . 915E+09 CS-136 .108E+11 .982E+10 .289E+11 .000E+00 . ll5E+11 .235E+10 . 439E+09 CS-137 .213E+ll .257E+l2 .301E+12 .000E+00 . 808E+11 .327E+11 . 94tE+09 BA-140 .619E+08 .120E+10 .120E+07 .000E+00 . 285E+06 .738E+06 . 295E+09 CE-141 .155E+05 .216E+06 .132E+06 .000E+00 . 407E+05 .000E+00 . 682E+08 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHD A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION IIP-1-230, Revision 4 85 At t aclimen t 10.16 (6 of 19) 4
, . - - . , _ . _ - . - - - , - -.--v-.,w-. . - ,s -ww .-.- *.,,e4- .-e',.,w ov -s -,----------rw- , e-me---re.-..+r- --eeu,- -
--+--e r--y -v- -,e- - ,-~n ---i
f TABLE 10 (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R
. 1 EHVIROHMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR CASE 00S DISCHARGES PATHWAY: COWS MILK (COHTAMINATED FORAGE) AGE GROUP: CHIED ( 2 0F 4 )
HUCLIDE ORGAN D0SE FACT 0RS ( SQ. METER-MREM /YR PER UCI/SEC )
TOTAL BODY BONE LIVER THYROID KIDHEY LUNG GI-LLI
.157E+04 .000E+00 .157E+04 .157E+04 .157E+04 .tS7E+04 .157E+04
,H----3 .269E+08 CR--51 .508E+06 .000E+00 .000E+00 .282E+06 .770E+05 .515E+06
.279E+08 .000E+00 .105E+09 .000E+00 .294E+08 .000E+00 .879E+08 MH--54 FE--59 .483E+09 .600E+09 .970E+09 .000E+00 .000E+00 .28tE+09 .10iE+f0 i C0--58 .185E+09 .000E+00 .605E+08 .000E+00 .000E+00 .000E+00 .353E+09 CO--60 .636E+09 .000E+00 .216E+09 .000E+00 .000E+00 .000E+00 .120E+10 2H--65 .342E+11 .20?E+11 .550E+11 .000E+00 .347E+11 .000E+00 .966E+10 SR--89 .943E+09 .330E+11 .000E+00 .000E+00 .000E+00 .000E+00 .128E+10
.142E+12 .558E+12 .000E+00 .000E+00 .000E+00 .000E+00 .752E+10 SR--90 2R--95 .374E+04 .19tE+05 .42tE+04 .000E+00 .602E+04 .000E+00 .439E+07 I--131 .743E+09 .130E+10 .13tE+10 .432E+12 .215E+10 .000E+00 .it6E+09
.805E+07 .172E+08 .213E+08 .395E+10 .354E+08 .000E+00 .857E+07 I--133 .992E+09 CS-134 .388E+11 .ll2E+12 .tG4E+12 .000E+00 .570E+11 .205E+11
.894E+10 .503E+10 .138Ett! .000E+00 .736E+10 .110E+10 .486E+09 CS-136 .18tE+11 .966E+09 CS-137 .220E+11 .16tE+12 .154E+12 .000E+00 .503E+11 s
.341E+08 .584E+09 .SilE+06 .000E+00 .167E+06 .305E+06 .296E+09 BA-140 .679E+08 CE-141 .809E+04 .109E+06 .544E+05 .000E400 .239E+05 .000E400 i
BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, 1 DEPLETED X/0 AHD RELATIVE DEPOSITION I !!P-t-230, Revision 4 86 Attachment 10.16 (7 of 19) ,
_ -. _ _ . . - . - - _ . - _ . . _ , ,_ . . - _ . _ . _ - - ~ . . _ , - . . - . . . _ . - - - , - _ _ - , - - , _ . _ . - _ , _ . - . , _ _ _ _ _ . . . -
TABLE 10 (CON'T) .
PATifWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER TilAN NOBLE GASES, R i
ENVIROHNENTAL PATHWAY-DOSE CONVERSIGH FACTORS R<I) FOR CASEOUS DISCHARGES PATHWAY: COWS MILK (CONTANIHATED FORACE) AGE GROUP: TEEN ( 3 0F 4 )
HUCLIDE ORCAH D0SE FACT 0RS ( SQ.NETER-NREM/YR PER UCI/SEC )
TOTAL BODY BONE LIVER THYROID KIDHEY LUHG GI-LLI H- --3 .994E+03 .000E+00 .994E+03 .994E+03 .994E+03 .994E+03 .994E+03 CR--51 .249E+06 .000E+00 .000E+00 .138E+06 .546E+05 .355E+06 .418E+08
,139E+08 .000E+00 .700E+08 .000E+00 .209E+08 .000E+00 .144E+09 MH -54 .190E+09 .143E+10 FE -59 .233E+09 .259E+09 .604E+09 .000E+00 .000E+00 C0--58 .983E+08 .000E+00 .396E+08 .000E+00 .000E+00 .000E+00 .546E+09 CO--60 .313E+09 .000E+00 .139E+09 .000E+00 .000E+00 .000E+00 .18tE+10
.170E+11 .105E+11 .365E+11 .000E+00 .234E+11 .000E+00 .155E+11 ZH--65 .159E+10 SR--89 .382E+09 .133E+11 .00AE+00 .000E+00 .000E+00 .000E+00 SR--90 .816E+11 .330E+12 .0boE+00 .000E+00 .000E+00 .000E+00 .92SE+10 2R--95 .179E+04 .824E+04 .260E+04 .000E+00 .382E+04 .000E+00 .600E+07
.403E+09 .536E+09 .750E+09 .219E+12 .129E+10 .000E+00 .148E+09 I--131 I--133 .366E+07 .708E+07 .120E+08 .168E+10 .211E+08 .000E+00 .908E+07 CS-134 .531E+11 .486E+11 .114E+12 .000E+00 .364E+ll .139E+11 .142E+10 CS-136 .589E+10 .223E+10 .877E+10 .000E+00 .477E+10 .752E+09 .705E+09 CS-137 .310E+11 .669E+11 .890E+11 .000E+00 .303E+11 .ll8E+11 .127E+10 BA-140 .156E+08 .242E+09 .296E+06 .000E+00 .100E+06 .199E+06 .373E+09
.340E404 .443E405 .296E+05 .000E400 .139E405 .000E+00 .846E408 CE-141 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AllD A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION llP-1-230, Revision 4 87 At t acliment 10.16 (8 of 19)
TABLE 10 (CON'T)
PATifWAY DOSE FACTORS DUE TO HAD10NUCLIDES OTilER TilAN NOBLE GASES, R, ,
\
ENVIRGHNEHTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR CASEQUS DISCHARGES AGE GROUP: ADULT (4 0F 4 )
PATHWAY: COWS MILK (CONTANIHATED FORAGE)
ORGAH D0SE FACT 0RS ( SO.NETER-NREN/YR PER UCI/SEC )
HUCLIDE _______
BONE LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY ________ ________ ________ ________
.763E+03 .763E+03 .763E+03 .763E+03 .763E+03 H----3 .763E+03 .000E+00 .189E+06 .359E408
.143E+06 .000E+00 .000E+00 .852E+05 .314E+05 CR--51 .125E+08 .000E+00 .129E+09 NH--54 .802E+07 .000E+00 .420E+08 .000E+00
.148E+09 .348E+09 .000E+00 .000E+00 .973E+08 .ll6E+10 FE--59 .133E+09 .000E+00 .477E+09
.528E+08 .000E+00 .235E+08 .000E+00 .000E+00 C0--58 .000E+00 .000E+00 .154E+10 C0--60 .18tE+09 .000E+00 .820E+08 .000E+00
.218E+11 .000E+00 .146E+11 .000E+00 .137E+11 2H--65 .986E+10 .6SSE+10
.724E+10 .000E+00 .'000E+00 .000E+00 .000E+00 .ti6E+10 SR--89 .208E+09 .000E+00 .676E+10
.374E+11 .234E+12 .000E+00 .000E+00 .000E+00 SR--90 .237E+04 .000E+00 .479E+07 2R--95 .302E+04 .47tE+04 .15tE+04 .000E+00
.295E+09 .423E+09 .138E+12 .724E+09 .000E+00 .lllE+09 I--131 .242E+09 .000E+0C .606E+07 I--133 .205E+07 .3S8E+07 ' 674E+07
. .991E+09 .ll8E+08
.280E+11 .666E+11 .000E+00 .216E+11 .716E+10 .ll7E+10 CS-134 .545E+11 .394E+09 .537E+09
.372E+10 .13tE+10 .517E+10 .000E+00 .287E+10 CS-136 ,000E+00 .l?tE+11 .569E+10 .977E+09 CS-137 .33tE+11 .369E+11 .505E+11
.168E+06 .000E+00 .572E+05 .964E+05 .276E409 BA-140 '
'.878E+07 .134E+09
.000E+00 .759E+04 .000E+00 .625E+08 CE-141 .185E+04 .242E+05 .163E+05 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF I FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION gg At taclunent 10.16 (9 of 19) llP-1-230, Revision 4
TABLE la (CON'T) .
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3 FOR GASEQUS DISCHARGES ENVIROHNENTAL f ATHWAY-DOSE CONVERS10H FACTORS R( I)
AGE GROUP: CHILD (1 0F 3) ,
PATHWAY: NEAT (COHTANIHATED FORAGE)
D0SE FACT 0RS ( SO.NETER-NREN/YR PER UCI/SEC )
HUCLIDE ORGAN -------------------------------
-- CI-LLI TOTAL BODY BONE ---------------THYROID LIVER KIDHEY LUHG
,234E+03 .234E+03 .234E+03
.000E+00 .234E+03 .234E+03 .464E+06 H----3 .234E+03 .486E+04 .133E+04 .88?E+04
.875E+04 000E+00 .000E+00 .000E+00 .672E+07 CR--Si .800E+07 .000E+00 ,224E+07 NH--54 .213E+07 000E+00 .000E+00 .176E+09 .63tE+09
.375E+09 .606E+09 .000E+00 .955E+08 FE--59 .302E+09 .000E+00 .000E+00 .000E+00
.501E+08 000E+00 .164E+08 .000E+00 .384E409 CO--58 .693E+08 .000E+00 ,000E+00 00--60 .204E+09 .000E+00 .629E+09 .000E+00 .175E+09
.375E+09 .999E+09 .000E+00 .186E+08 ZH--65 .62tE+09 .000E+00 .000E+00 .000E+00
.137E+08 .480E+09 .000E+00 .000E+00 .140E+09 SR--89 .000E+00 .000E+00 .000E+00 SR--90 .264E+10 .104E+11 .836E406 .000E+00 .609E409
.266E+07 .584E+06 .000E+00 .147E+07 2R--95 .520E+06 .547E+10 .272E+08 .000E+00
.941E+07 .165E+08 .166E+08 .000E+00 .286E400 I--131 .574E+00 .710E+00 .132E+03 .ll8E+01
.002E+07 I--133 .269E+00 .000E+00 .461E+09 .165E+09
.314Et09 .90?E+09 .149E+10 .349E+07 .154E+07 CS-134 .439E+08 .000E+00 .234E+08 CS-136 .284E+08 .160E+08 .416E+09 .150E+09 .799E+07
.133E+10 .128E+10 .000E+00 .220E+08 CS-137 .188E+09 .000E+00 .124E+05 .227E+05
.254E+07 .435E+08 .38tE+05 .000E+00 .138E+08 BA-140 .it0E+05 .000E+00 .484E+04 CE-141 .164E+04 .221E+05 1
UCI/SEC RELEASE RATE OF EACH ISOTOPE I AllD A VALUE OF 1 FOR X/0, BASED OH 1 DEPLETED X/O AND RELATIVE DEPOSITION j
89 Attachment. 10.16 (10 of 19) ilP-1-230. Revision 4
TABLE 10 (CON'T)
PATilWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER TilAN N0BLE GASES, R 1 ENVIROHNEHTAL PATHWAY-DOSE COHVERSIGH FACTORS RCI) FOR CASE 00S DISCHARGES AGE GROUP: TEEH (2 0F 3)
PATHWAY: NEAT (COHTANINATED FORAGE)
ORCAH D0SE FACT 0RS ( SO.NETER-NREN/YR PER UCI/SEC )
HUCLIDE
--_-_-- ---___--_----_--__---_----_-_---__-__--_----___-__---_____-----________ LUHG GI-LLI TOTAL BODY B0HE LIVER THYROID KIDHEY
.000E+00 .194E+03 .194E+03 .194E+03 .194E+03 .194E+03 H----3 .194E+03 .123E+04 .801E+04 .943E+06 CR--51 .56fE+04 .030E+00 .000E+00 .312E+04
.700E+0? .000E+00 .209E+07 .000E+00 .143E+08 NH--54 .139E+0? .000E+00
.190E+09 .211E+09 .493E+09 .000E+00 .000E+00 .156E+09 .it7E+f0 FE--59 .000E+00 .193E+09 CO--58 .323E+08 .000E+00 .140E+08 .000E+00 .000E+00
.000E+00 .583E+08 .000E+00 .000E+00 .000E+00 .760E+09 CO--60 .13tE+09 .000E+00 .367E+09 2H--65 .405E+09 .250E+09 .868E+09 .000E+00 .555E+09
.253E+09 .000E+00 .000E+00 .000E+00 .000E+00 .302E+08 SR--89 .726E+07 .000E+00 .226E+09 SR--90 .199E+10 .805E+10 .000E+00 .000E+00 .000E+00
.150E+07 .472E+06 .000E+00 .693E+06 .000E+00 .109E+10 2R--95 .325E+06 .000E+00 .246E+07 I--131 .667E+07 .887E+07 .124E+08 .363E+10 .214E+08
.309E+00 .524E+00 .732E+02 .920E+00 .000E+00 .397E+00 I--133 .160E+00 .385E+09 .147E+09 .15tE+08 CS-134 .562E+09 .514E+09 .121E+10 .000E+00
.365E+08 .000E+00 .198E+08 .313E+07 .293E+07 CS-136 .245E+08 .926E+07 .137E+08
,335E+09 .724E+09 .963E+09 .000E+00 .328E+09 .127E+09 CS-137 .980E+04 .194E+05 .364E+08 BA-140 .152E+07 .236E+08 .289E+05 .000E+00
.784E+04 .000E+00 .369E+04 .000E+00 .224E+08 i CE-141 .901E+03 .117E+05 I
8ASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF l FOR X/0, DEPLETED X/O AHD RELATIVE DEPOSITI0H l
t ilP-1-230, Revision 4 90 Attachment 10.16 (llof 19) 4
l TABLE 10 (CON'T)
~
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i
EHVIROHNENTAL PATHWAY-DOSE COHVERSIGH FACTORS R< I ) FOR GASEGUS DISCHARGES AGE GROUP: ADULT ( 3 0F 3 )
PATHWAY: MEAT (COHTAMIHATED FORAGE)
HUCLIDE ORGAH D0SE FACTORS (SO.NETER-NREH/YR PER UCI/SEC)
BONE LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY -------- -------- -------- --------
.325E+03 .000E+00 .325E+03 .325E+03 .325E+03 .325E+03 .325E+03 H----3 .155E+04 .931E+04 .176E+07 CR--51 .702E+04 .000E+00 .000E+00 .419E+04
.l?5E+07 .000E+00 .917E+07 .000E+00 .273E+07 .000E+00 .28tE+08 NH--54 .000E+00 .174E+09 .207E+10 FE--59 .238E+09 .264E+09 .62tE+09 .000E+00
.000E+00 .182E+08 .000E+00 .000E+00 .000E+00 .368E+09 CO--58 .408E+08 .000E+00 C0--60 .166E+09 .000E+00 .752E+08 .000E+00 .000E+00 .14tE+10
.355E+09 .ll3E+10 .000E+00 .756E+09 .000E+00 .712E409 2H--65 .SilE+09 .482E+08
.862E+07 .300E+09 .000E+00 .000E+00 .000E+00 .000E+00 SR--89 .000E+00 .000E+00 .000E+00 .359E+09 SR--90 .305E+10 .124E+11 .000E+00
.187E+07 .599E+06 .000E+00 .940E+06 .000E+00 .190E+10 2R--95 .406E+06 .000E+00 .403E+07
.875E+07 .107E+08 .153E+08. .501E+10 .262E+08 I--131 .000E+00 .578E+00 I--133 .196E+00 .370E+00 .643E+00 .945E+02 .ll2E+01
.647E+09 .154E+10 .000E+00 .498E+09 .165E+09 .269E+08 C5-134 .126E+10 .358E+07 .533E+67
.338E+08 .119E+0B .469E+08 .000E+00 .261E+08 C5-136 .405E+09 .135E+09 .231E408 CS-13? .781E409 .872E+09 .119E+10 .000E+00
.285E+08 .358E+05 .000E+00 .122E+05 .205E+05 .587E+08 94-140 .187E+07 .000E+00 .362E408
.107E+04 .140E+05 .946E+04 .000E+00 .440E+04 CE-141 DASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, 1 DEPLETED X/O AHD RELATIVE DEPOSITION IIP-1-230, Revision 4 91 Attachment 10.16 (12 of 19)
. _ - - . _ . . .~. .
TABLE IS (CON'T)
PATlWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER TilAN NOBLE GASES, R 1
ENVIROHNENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR CASE 00S DISCHnRGES t.
ACE CROUP: CHILD (1 0F 3)
PATHWAY: LEAFY VEGETABLES ORGAH D0SE FACTORS (SQ.NETER-NREN/YR PER UCI/SEC )
HUCLIDE ______________
_________________________________________________________Y B0HE LIVER THYROID KIDHE LUHG CI-LLI TOTAL BODY ________ ________ ________ ________
.400E+04 .400E+04 .400E+04 .400E+04 .400E+04 H----3 .400E+04 .000E+00 .617E+0?
.000E+00 .000E+00 .645E+05 .176E+05 .Il8E+06 CR--51 .ll6E+06
.000E+00 .186E+09 .000E+00 .557E+09
.l?7E+09 .000E+00 .664E+09 Mil--54
.639E+09 .000E+00 .000E+00 .185E+09 .665E+09 FE--59 .318E+09 .395E+09 .374E+09
.000E+00 .64tE+08 .000E+00 .000E+00 .000E+00 CD--58 .196E+09 .000E+00 .000E+00 .210E+10 CD--60 .ll2E+10 .000E+00 .378E+09 .000E+00
.216E+10 .000E+00 .136E+10 .000E+00 .380E+09 2H--65 .334E+10 .8tlE+09
.000E+00 .000E+00 .138E+10 SR--89 .302E+10 .357E+11 .000E+00 .000E+00
.000E400 .000E+00 .000E+00 .000E+00 .167E+11 SR--90 .315E+12 .324E+13 .000E+00
.752E+06 .384E+07 .844E+06 .000E+00 .12tE+07 .88tE+09 2R--95 .235E+09 .000E+00 .128E+08
.815E+08 .143E+09 .143E+09 .474E+11 I--131
.437E+07 . 812E+09 .729E+07 .000E+00 .176E+07 I--133 .165E+07 .354E+07 .l38E+09
.538E+10 .155E+ll .255E+11 .000E+00 .790E+10 .284E+l0 CS-134 .119E+09 .177E+08 .783E407
.000E+00 CS-136 ;144E+09 .81tE+08 .223E+09
.000E+00 .746E+l0 .268E+10 .143E+09 CS-137 .338E+10 .239E+11 .229E+ll
.143E+06 .139E+09
.160E+08 .275E+09 .24tE+06 .000E+00 .783E+05 B A- 14 0
.325E+06 .000E+00 .143E+06 .000E+00 .406E+09 CE-141 .483E+05 .652E+06
)
BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND 4 VALUE OF 1 FOR X/0, DEFLETEb X/0 AND RELATIVE DEPOSITION IIP-1-230, Revision 4 92 Attachment 10.16 (13 of 19) s
TABLE 19 (CON'T)
PATlWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 1
EHVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR GASEGUS DISCHARGES AGE GROUP: TEEN (2 0F 3)
PATHWAY: LEAFY YEGETABLES HUCLIDE ORGAH D0SE FACT 0RS ( SQ.NETER-NREN/YR PER UCI/SEC )
BONE LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY -------- -_---__. __--_--- ___---__
H----3 .259E+04 .000E+00 .259E+04 .259E+04 .259E+04 .259E+04 .259E+04
.513E+05 .000E+00 .000E+00 .340E+05 .134E+05 .875E+05 .103E+08 CR--51 .000E+00 HH--54 .900E+08 .000E+00 .454E+09 .000E+00 .135E+09 .93tE+09
- .983E+09 4
FE--59 .16tE+09 .178E+09 .416E+09 .000E+00 .000E+00 .13tE+09
.100E+09 .000E+00 .434E+08 .000E+00 .000E+00 .000E+00 .599E+09 i C0--58 .000E+00 .324E+10 CO--60 .560E+09 .000E+00 .249E+09 .000E+00 .000E+00 i
.685E+09 .423E+09 .147E+10 .000E+00 .940E+09 .000E+00 .622E+09 2H--65 .000E+00 .t?9E+10 5R--89 .431E+09 .150E+tl .000E+00 .000E+00 .000E+00
.tG5E+12 .75tE+12 .000E+00 .000E+00 .000E+00 .000E+00 .21tE+11
- SR--90 .000E+00 .125E+to 2R--95 .372E+06 .17tE+07 .54tE+06 .000E+00 .795E+06
.767E+08 .107E+09 .313E+11 .185E+09 .000E+00 .212E+08 I--131 .577E+08 .249E+07 I--133 .100E+07 .194E+07 .329E+07 .459E+09 .577E+07 .000E+00
.689E+10 .162E+11 .000E+00 .515E+10 .197E+10 .202E+09 CS-134 .752E+10 .137E+08
.114E+09 .43tE+08 .l?0E+09 .000E+00 .924E+08 .146E+08 CS-136 -
.192E+09 CS-137 .469E+10 .10tE+11 .135E+11 .000E+00 .459E+10 .178E+10
.137E+09 .168E+06 .000E+00 .570E+05 .113E+06 .212E+09 BA-140 .884E+07 .537E+09
.216E+05 .28tE406 .188E+06 .000E+00 .884E+05 .000E+00 4 CE-141 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION IIP-1-2 30, Revision 4 93 At taciunent 10.16 (14 of 19)
TABLE 10 (CON'T) .
PATilWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER
. THAN NOBLE GASES, R i
ENVIROHNENTAL PATHWAY-DOSE COllVERSION FACTORS R( ! ) FOR GASEQUS DISCHARGES AGE GROUP: ADULT (3 0F 3)
PATHWAY: LEAFY VEGETABLES ORGAH D0SE FAC70RS (SO.NETER-NREM/YR PER UCI/SEC )
HUCLIDE BONE LIVER THYROID KIDHEY LUHG GI-LLI TOTAt BODY -- ----- -------- -------- --------
.000E+00 .226E+04 .226E+04 .22.6E+04 .226E+04 .226E+04 H----3 .226E+04 .613E+05 CR--51 .462E+05 .000E+00 .000E+00 .276E+05 .102E+05 .ll6E+08
.000E+00 .313E+09 .000E+00 .930E+08 .000E+00 .958E+09 NH--54 .597E+08 .823E+08 .982E+09 FE--59 .Il3E+09 .125E+09 .295E+09 .000E+00 .000E+00
.000E+00 .306E+08 .000E+00 .000E+00 .000E+00 .62tE+09 C0--58 .686E+08 .000E+00- .314E+10 CD--60 ,369E+09 .000E+00 .l67E409 .000E+00 .000E+00
.317E+09 .101E+10 .000E+00 .674E+09 .000E+00 .635E+09 2H--65 .456E+09 .000E+00 .159E+10 SR--89 .284E+05 .990E+10 .000E+00 .000E+00 .000E+00
.605E+12 .000E+00 .000E+00 .000E+00 .000E+00 .175E+11 SR--90 .348E+12 .000E+00 .119E+10 2R--95 .254E+06 .ll?E+07 .375E+06 .000E+00 .589E+06
.806E+08 .ll5E+09 .378E+11 .198E+09 .000E+00 .304E+08 I--131 .66tE+08 .000E+00 .326E+07
.lllE+07 .209E+07 .363E+07 .534E+09 .634E+07 I--133 .189E+09 CS-134 .882E+10 .453E+10 .108E+11 .000E+00 .349E+10 .Il6E+10
.422E+08 .167E+09 .000E+00 .927E+08 .127E+08 .189E+08 CS-136 .120E+09 .981E+09 .168E+09 CS-137 .570E+10 .636E+10 .870E+10 .000E+00 .295E+10
.128E+09 .161E+06 .000E+00 .546E+05 .919E+05 .263E+09 BA-140 .637E+07 .000E+00 .507E409 CE-141 .150E+05 .196E+06 .133E+06 .000E+00 .616E+05 BASED Gil i UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITIOli IIP-1-230, Revision 4 Attachment 10.16 (15 of 19)
! 94
. TABLE 10 (CON'T) .
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER
. TilAN NOBLE GASES, R g EHVIROHNENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR CASE 00S DISCHARCES PATHWAY: GOATS MILK (CoHTANIHATED FORAGE)
AGE GROUP: INFANT < t OF 4 )
HUCLIDE ORGAH D0SE FACT 0RS (SQ.NETER-NREN/YR PER UCI/SEC)
BONE LIVER THYROID KIDHEY LUHG GI-LLI TOTAL BODY -------- -------- -------- --- ----
H----3 .405E+05 .000E+00 .405E+05 .405E+05 .405E+05 .405E+05 .405E+05
.966E+05 .000E+00, .000E+00 .630E+05 .138E+05 .123E+06 .281E+07 CR--51 .000E+00 .859E+07 NH--54 .530E+07 .000E+00 .234E+08 .000E+00 .518E+07 FE--59 .100E+08 .146E+08 .254E+08 .000E+00 .000E+00 .75tE+07 .12tE+08
.360E+08 .000E+00 .145E+08 .000E+00 .000E+00 .000E+00 .362E+08
- C0--58 .126E+09 CD--60 .125E+09 .000E+00 .529E+08 .000E+00 .000E+00 .000E+00
.527E+10 .333E+10 .114E+11 .000E+00 .554E+10 .000E+00 .964E+10 ZH--65 SR--89 .378E+10 .132E+12 .000E+00 .000E+00 .000E+00 .000E+00 .27tE+10
.325E+12 .128E+13 .000E+00 .000E+00 .000E+00 .000E+00 .159E+11 SR--90 .000E+00 .495E+06 ZR--95 .705E+03 .408E+04 .994E+03 .000E+00 .l07E+04
.169E+10 .326E+10 .384E+10 .126E+13 .448E+10 .000E+00 .137E+09 I--131 .107E+08 l--133 .386E+08 .436E+08 .635E+08 .115E+11 .840E+08 .000E+00 CS-134 .102E+12 .542E+12 .101E+13 .000E+00 .260E+12 .107E+12 .275E+10
.324E+11 .295E+11 .867E+11 .000E+00 .345E+11 .706E+10 .132E+10 CS-136 CS-137 .640E+11 .772E+12 .903E+12 .000E+00 .242E+12 .982E+ll .282E+10 BA-140 .743E+07 .144E+09 .144E+06 .000E+00 .342E+05 .885E+05 .354E+08
.260E+05 .158E+05 .000E+00 .488E+04 .000E+00 .818E+07 CE-141 .186E+04 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/0 AllD RELATIVE DEPOSITI0H llP-t-230, Revision 4 95 At t acliment. 10.16 (16 of 19)
TABLE IG (CON'T)
PATilWAY DOSE FACTORS DUE TO RADIONUCLIDES OillER
. TilAN NOBLE GASES, R 1
ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAYS GOATS HILK (COHTAHIHATED FORAGE) AGE GROUP: CHILD (2 0F 4 )
HUCLIDE ORGAH D0SE FACT 0RS ( SQ.NETER-HREH/YR PER UCI/SEC )
BONE LIVER TH'tROID KIDHEY LUHG GI-LLI TOTAL BODY -------- -------- -------- --------
.267E+05 .000E+00 .267E+05 .267E+05 .267E+05 .267E+05 .267E+05 H----3 .618E+05 .323E+07 CR--51 .609E+05 .000E+00 .000E+00 .338E+05 .924E+04
.335E+07 .000E+00 .126E+08 .000E+00 .353E+07 .000E+00 .106E+08 HH--54 .366E+07 FE--59 .629E+07 .780E+07 .126E+08 .000E+00 .000E+00 .f3fE+08
.222E+08 .000E+00 .727E+07 .000E+00 .000E+00 .000E+00 .424E+08 CO--58 .000E+00 . .143E+09' CD--60 .764E+08 .000E+00 .259E+08 000E+00 .000E+00
.4ttE+10 .248E+10 .660E+10 .000E+00 .416E+10 .000E+00 .it6E+10 2H--65 .268E+10 SR--89 .198E+10 .694E+11 .000E+00 .000E+00 .000E+00 .000E+00
.000E+00 .000E+00 .000E+00 .000E+00 .158E+11 SR--90 .297E+12 .tl7E+13
.527E+06
.449E+03 .230E+04 .505E+03 .000E+00 .722E+03 .000E+00 2R--95 .000E+00 .140E+09 I--131 .892E+09 .tS6E+10 .157E+10 .St9E+12 .258E+10
.206E+08 .255E+08 .474E+10 .425E+08 .000E+00 .103E+08 I--133 .966E+07 .614E+11 CS-134 .fl6E+12 ,337E+12 .552E+l2 .000E+00 .17tE+12 .298E+10
.268E+11 .tStE+11 .415E+11 .000E+00 .22tE+11 .329E+10 .146E+10 CS-136 .543E+11 .290E+10 CS-137 .683E+11 .484E+12 .463E+12 .000E+00 .tStE+12
,409E+07 .701E+08 .614E+05 .000E+00 .200E+05 .366E+05 .355E+08 BA-140 .286E+04 .000E+00 .815E+07 CE-141 .970E+03 .13tE+05 .653E+04 .000E+00 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION llP-1-230 Revision 4 96 m gm g g ( g 7 g pg
TABLE 10 (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R( I) FOR CASE 00S DISCHARCES AGE GROUP: TEEN ( 3 0F 4 )
PATHWAY: GOATS MILK (CONTAMINATED FORAGE)
HUCLIDE ORGAH D0SE FACT 0RS (SQ. METER-MREN/YR PER UCI/SEC)
BONE LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY ________ ________ ________ ________
.000E+00 .169E+05 .169E+05 .169E+05 .169E+05 .169E+05 H----3 .369E+05 .427E+05 .502E+07 CR--51 .299E+05 .000E+00 .000E+00 .166E+05 .655E404
.000E+00 .84tE+07 .000E+00 .25tE+07 .000E+00 .172E+08 MH--54 .167E+07 .247E+07 .186E+08 FE--59 .303E+07 .336E+07 .785E+07 .000E+00 .000E+00
.000E+00 .476E+07 .000E+00 .000E+00 .000E+00 .656E+08 CD--58 .110E+08 .000E+00 .217E+09 CD--60 .376E+0S .000E+00 .167E+08 .000E+00 .000E+00
.126E+10 .439E+10 .000E+00 .281E+10 .000E+00 .186E+10 2H--65 .205E+10 .000E+00 .334E+10 SR--89 .802E+09 .280E+11 .000E+00 .000E+00 .000E+00
.694E+12 .000E+00 .000E+00 .000E+00 .000E+00 .195E+11 SR--90 .17tE+12 .000E+00 .720E+06 2R--95 .214E+03 .988E+03 .312E+03 .000E+00 .458E+03
.643E+09 .901E+09 .263E+12 .155E+10 .000E+00 .178E+09 I--131 .484E+09 .000E+00 .109E+08
.440E+07 .850E+07 .144E+08 .201E+10 .253E+08 I--133 .109E+12 .417E+11 .427E+10 CS-134 .159E+12 .146E+12 .343E+12 .000E+00
.669E+10 .263E+11 .000E+00 .143E+11 .226E+10 .212E+10 CS-136 .l??E+18 .909E+11 .353E+11 .380E+10 CS-137 .930E+11 .201E+12 .267E+12 .000E+00
.290E+08 .356E+05 .000E+00 .12tE+05 .239E+05 .448E+08
^
BA-140 .187E+07 .000E+00 .102E+08
.408E+03 .532E+04 .355E+04 .000E+00 .167E+04 CE-141 i
BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHD A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION i
IIP-1-230, Revision 4 97 At t acliment 10.16 (18 of 19)
TABLE IS (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 1
f ENVIRONMEHTAL PATHWAY-DOSE CONVERSIGH FACTORS R(I) FOR CASEOUS DISCHARGES ACE GROUP: ADULT (4 0F 4 )
PATHWAY: GOATS MILK (C0HTAMIHATED FORACE)
ORGAN D 0 S.E FACTORS (SQ. HETER-NREN/YR PER UCI/SEC )
HUCLIDE ------
LUNG TOTAL BODY BONE LIVER THYROID KIDHEY GI-LLI
.000E+00 .130E+05 .130E+05 .130E+05 .130E+05 .130E+05 H----3 .130E+05 .377E+04 .227E+05 .430E+07 CR--51 .171E+05 .000E+00 .000E+00 .102E+05
.505E+07 .000E+00 .150E+07 .000E+00 .155E+08 HH--54 .963E+06 .000E+00 .127E+07 .15tE+08
.174E+07 .193E+07 .453E+07 .000E+00 .000E+00 FE--59 .000E+00 .000E+00 .573E+08 CD--58 .633E+07 .000E+00 .282E+07 .000E+00
.984E+07 .000E+00 .000E+00 .000E+00 .185E+09 C0--60 .287E+08 .000E+00 .000E+00 .165E+10 2N--65 .ftBE+10 .823E+09 .262E+10 .000E+00 .l?5E+10
.000E+00 .000E+00 .000E+00 .000E+00 .244E+10 SR--89 .436E+09 .tS2E+11 .000E+00 .142E+tt
.12tE+12 .49tE+12 .000E+00 .000E+00 .000E+00 SR--90 .000E+00 .284E+03 .000E+00 .575E+06 2R--95 .323E+03 .565E+03 .18tE+03
.000E+00 .134E+09
.355E+09 .507E+09 .166E+12 .669E+09 I--131 .29tE+09 .141E+08 .000E+00 .727E+07
.247E+07 .465E+07 .809E+07 .119E+10 I--133
.200E+12 .000E+00 .647E+11 .2tSE+11 .350E+10 CS-134 .163E+12 .840E+11 .176E+10
.393E+10 .155E+11 .000E+00 .863E+10 .ll8E+10 CS-136 .ll2E+11
.000E+00 .514E+11 .171E+11 .293E+10 CS-137 .992E+11 .tllE+12 .tStE+12
.202E+05 .000E+00 .68?E+04 .tl6E+05 .331E+08 8A-140 .105E+07 .16fE+08 .000E+00 .750E+07
.223E+03 .290E+04 .196E+04 .000E+00 .9tlE+03 CE-141 8ASED OH i UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITI0H 98 Attachment 10.16 (19 of 19)
I!P-1-230, Revision 4
r --
FIGURE 7 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) 10-3 ,
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l i lilli i III lill l I I iIll 1 l
10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Obtained from Regulatory Guide 1.111 (March, 1976)
HP-1-230, Rev. 4 99 Attachment 10.17 (1 of 1)
TABLE 11 ANNUAL. AVERAGE DISPERSION PARAMETERS AT OR BEYOND THE UNRESTRICTED
$a AREA BOUNDARY
- - AMMUAL AVERAGE CNI/O (SEC/ METER CUSED) SISTANCE IN MILES 4.000 4.500 0.500 0.750 1 000 1.500 2.000 2.500 3.000 3.500
/3 SECTOR 0.250 S 3.048E-05 9.309E-04 4.85SE-04 2.454E-04 9.924E-07 5.451E-07 3.518E-07 2.490E-07 1.875E-07 1 476E-07 1.201E-07 SIW 3.794E-05 1.150E-05 5 947E-06 3.009E-04 1.215E-04 4.472E-07 4.307E-07 3.049E-07 2.29&E-07 1.007E-07 1.471E-07 g SW 5.090E-05 1.532E-05 7 903E-04 3.975E-04 1 603E-04 S.810E-07 5.498E-07 4.040E-07 3.044E-07 2.401E-07 1.954E-07
< CSU 5.144E-05 1.54eE-05 7 917E-04 3.987E-04 1.&t3E-06 S.904E-07 5.782E-07 4.111E-07 3.10SE-07 2.455E-07 2.003E-07 W 2.840E-05 S.434E-04 4.461E-04 2.25SE-04 9 17&E-07 5.049E-07 3.289E-07 2.33SE-07 1 7&&E-07 1.194E-07 1.137E-07 e WNW 5.389E-05 1.433E-05 8.485E-04 4.300E-04 1.748E-04 9.444E-07 4.245E-07 4.431E-07 3.343E-07 2.434E-07 2.14SE-07 NW 7.591E-05 2.274E-05 1.159E-05 5.815E-04 2.344E-04 1.29&E-06 S.452E-07 4.032E-07 4.573E-07 3 421E-07 2.941E-07 NFW 9.40SE-05 2.847E-05 1 429E-05 7.113E-04 2.847E-04 1.577E-06 1.035E-04 7.421E-07 5.649E-07 4.40SE-07 3.481E-07 N 7.963E-05 2.340E-05 1 182E-05 5.898E-04 2.372E-04 1 31&E-04 S.434E-07 4.192E-07 4.713E-07 3.744E-07 3.071E-07 NME 7.231E-05 2.140E-05 1 070E-05 5.331E-04 2.140E-04 1.1SSE-04 7.797E-07 5.594E-07 4.260E-07 3.385E-07 2.770E-07 NE 4.576E-05 1 937E-05 9.590E-04 4.749E-06 1.894E-06 1 051E-04 4.92eE-07 4.984E-07 3.805E-07 3 030E-07 2.490E-07 ENE 7.052E-05 2.072E-05 1.023E-05 5.042E-04 2.020E-04 1.123E-04 7.40SE-07 5.33eE-07 4.07&E-07 3 248E-07 2.472E-07 E 5.347E-05 1.578E-05 7.791E-04 3.852E-04 1.533E-04 S.515E-07 5.610E-07 4.044E-07 3.091E-07 2 443E-07 2.024E-07 ESE 4.982E-05 1.47&E-05 7.381E-04 3.459E-04 1.45&E-04 0.042E-07 5.290E-07 3.003E-07 2.898E-07 2 305E-07 1.092E-07 SE 4.442E-05 1.398E-05 7.121E-04 3.543E-04 1.430E-04 7.SS5E-07 5.137E-07 3.643E-07 2.774E-07 2 197E-07 1.796E-07 SSE 4.549E-05 1.375E-05 7 0SSE-04 3.540E-04 1.430E-04 7 844E-07 5.097E-07 3.420E-07 2.734E-07 2 157E-07 1.760E-07 ANNUAL AVERAGE CNI/S (SEC/ METER CUSED)
DISTAMCE IN MILES 20.000 25.000 30.000 35.000 40.000 45.000 50.000 DEARING 5.000 7.500 10.000 15.000
'S 1.003E-07 5.320E-08 3.522E-08 2.079E-08 1 435E-08 1 070E-08 S.544E-09 7.024E-09 5.931E-09 5.111E-09 4.476E-09 SSW 1.22SE-07 4.524E-08 4.32JE-00 2 554E-08 1.765E-08 1.327E-08 1.052E-00 S.657E-09 7.313E-09 4.30&E-09 5.524E-09 SW 1.435E-07 S.71SE-08 5.791E-08 3.435E-08 2.379E-08 1.793E-08 1 424E-08 1.173E-08 9.923E-09 8 544E-09 7.510E-09
[* WSW 1.477E-07 8.987E-08 5 990E-08 3.54SE-08 2.478E-08 1.871E-08 1.4SSE-08 1.227E-08 1.039E-08 S.975E-09 7.875E-09 C) W 9.518E-08 5.090E-OS 3.387E-OS 2.012E-08 1.395E-08 1.0b1E-06 S.34SE-09 4 877E-09 5.014E-09 5.019E-09 4.400E-09
. WmW 1 794E-07 9.549E-08 4 352E-08 3.742E-08 2.402E-08 1.957E-08 1.553E-08 1.278E-00 1 000E-08 9.309E-09 S.15&E-09 NW 2.484E-07 1.340E-07 8.970E-08 5.375E-08 3.747E-00 2 837E-00 2.242E-08 1 849E-08 1.585E-08 1.371E-08 1.205E-08 ENW 3.09&E-07 1 40&E-07 1.137E-07 4.872E-08 4.821E-08 3.447E-00 2.934E-00 2.432E-00 2.06SE-08 1.793E-08 1.578E-08 N 2.582E-07 1.405E-07 9.447E-08 5.719E-08 4.009E-08 3.04SE-00 2.438E-08 2.020E-00 1.717E-08 1.4SSE-08 1.310E-08 NIE 2.33&E-07 1 274E-07 S.588E-08 5.195E-08 3.445E-00 2.773E-03 2.220E-08 1.840E-00 1.544E-08 1.35&E-08 1.194E-08 NE 2.098E-07 1.150E-07 7.795E-08 4.735E-08 3.334E-08 2.543E-OS 2.040E-08 1 494E-00 1.443E-08 1 253E-081.195E-08 1.104E-08 E NE 2.252E-07 1 237E-07 8.383E-08 5.10&E-08 3.59?E-00 2.74SE-08 2.205E-08 1.832E-03 1.561E-08 1.185E-08 1.356E-08 1.029E-08 9.076E-09 l E 1.707E-07 9 379E-08 4.358E-08 3.873E-03 2.731E-08 2.085E-08 1.904E-0811.527E-08 674E-08 11.267E-04 391E-Oli 1.078E-08 9.354E-09 8.243E-09 i ESE SE 1.592E-07 S.117E-08 1.504E-07 8.497E-085.433E-08 5.873E-083.255E-09 3.541E-082.270E-08 2.503E-08 1.718E-08 1.370E-00 1.133E-00 9.604E-09 8.311E-09 7.303E-09 SSE 1 472E-07 7.872E-08 5.241E-08 3.117E-00 2.144E-08 1.433E-08 1.290E-08 1.071E-01 9.043E-09 7.82SE-09 4.86BE-09 CH1/0 (SEC/ METER Cu6ED) FOR EACM SEGMENT SEGMENT BOUNDARIES IN MILES 4-5 5-10 10-20 20-30 30-40 40-50 1-2 2-3 3-4 DIRECTION .5-1 y Fkon SITE 1 890E-07 1.209E-07 5.547E-08 2.113E-08 1.084E-08 7.042E-09 5.119E-09 re S 4.700E-04 1.119E-04 3.622E-07 1.334E-00 0.478E-09 4.315E-09 L 1.370E-04 4.434E-07 2.325E-07 1.481E-07 4.82&E-08 2.596E-08 S.576E-09 Q SSW 5.883E-04 1.949E-07 9.114E-08 3.490E-08 1.002E-08 1.17&E-08 n SW 7.005E-06 1 809E-04 5.845E-07 3.004E-07 3.422E-08 1.SSOE-08 1.230E-08 8.987E-09 Of 1.820E-04 5.944E-07 3.14&E-07 2.016E-07 9.385E-08 USW 7.84&E-04 1 145E-07 5.317E-08 2 043E-08 1.056E-08 4.893E-09 5.026E-09 N 4.409E-06 1.033E-04 3.383E-07 1.788E-07 1.281E-08 9.322E-09 W
3.385E-07 2.142E-07 1.000E-07 3.822E-00 1.967E-08 WNW S.367E-06 1.967E-0'& 4.42&E-07 5 451E-00 2.850E-08 1.873E-08 1 373E-08
% 2.649E-06 S.686E-07 4.427E-07 2.980E-07 1.397E-07 1.795E-08 NW 1.150E-05 3.704E-07 1.755E-07 4.95?E-08 3.682E-00 2.437E-08 PMW 1.425E-05 3.231E-04 1.063E-04 5.713E-07 3.060E-08 2 024E-08 1.490E-08
[$ S.SeeE-07 4.766E-07 3.089E-07 1.443E-07 5.792E-08
- N 1.181E-05 2.684E-06 5.260E-08 2 784E-OS 1 843E-08 1.358E-08 2.42&E-04 8.003E-07 4.300E-07 2.794E-07 1.325E-07 1.254E-08
!$ N%E 1.069E-05 2.505E-07 1.194E-07 4.790E-08 2.553E-08 1 697E-08 9.612E-06 2.154E-06 7.10/E-07 3.U46E-07 1.835E-08 1.357E-08 NE 4.*41E-07 2.687E-07 1.285E-07 5.164E-00 2.758E-08 h) ENE 1.026E-05 2.297E-06 7.597E-07 3.918E-08 2.093E-08 1.393E-08 1.030E-08 1.745E-06 5.762E-07 3.124E-07 2.037E-07 9.746E-08 E 7.811E-04 1.903E-07 v.047E-C8 3.604E-08 1.914E-08 1.270E-08 9.367E-09 7.367E-06 1.657E-06 5.437E-07 2.931E-07 1.726E-08 1.135E-08 8.322E-09
!d ESE 5.2880-07 2.809E-07 1.807E-07 8.467E-08 3.301E-08 St' 7.063E-06 1.419E-06 8.22*aE-08 3.165E-08 1.641E-08 1. 07 3E -08 7.839E-09
" ~r , aaer.as e 4: 4- A A %.?44F-07 2.767E-07 1 771E-07
TABLE 12 AVERACE ANNUAL DEPOSITION PARAMETERS FOR AREAS AT OR BEYOND UNRESTRICTED AREA BOUNDARY m 888888888s38888888888 RELATIVE DEPOSITION PER UNIT AREA (H88-2) AT FIXED POINTS BY DOWHWIND SECTORS **sssssssssssssssses N Dt*ECTION DISTANCES IN. MILES
- d. f2%M SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 ,
8 S 1.059E-07 3.582E-08 1.839E-08 8.744E-09 3.14tE-09 1.558E-09 9.172E-10 6.006E-10 4.226E-10 3.132E-10 2.413E-10 E$ SSW 1.500E-07 5.072E-08 2.604E-08 1.238E-08 4.44?E-09 2 205E-09 1.299E-09 R.503E-10 5.983E-10 4.434E-10 3.417E-10 C) SW
- 2.136E-07 7.222E-08 3.708E-08 1.763E-08 6.332E-09 3 140E-09 1.849E-09 1.211E-09 8.519E-10 6.313E-10 4.865E-10 WSW 1.650E-07 5.580E-08 2.865E-08 1.362E-08 4.893E-09 2 426E-09 1.429E-09 9.355E-10 6.583E-10 4.878E-10 3.759E-10 W W 8.788E-08 2.972E-08 1.526E-08 7.254E-09 2.606E-09 1 292E-09 7.609E-10 4.982E-10 3.506E-10 2.598E-10 2.002E-10 k
WNW 1.835E-07 6.204E-08 3.185E-08 1.514E-08 5.440E-09 2 698E-09 1.588E-09 1.040E-09 7.319E-10 5.424E-10 4.180E-10 NW 2.144E-07 7.249E-08 3.722E-08 1.769E-08 6.356E-09 3 152E-09 1.856E-09 1.215E-09 8.551E-10 6.337E-10 4.884E-10 NNW p
N 2.242E-07 7.582E-08 3.893E-08 1.851E-08 6.448E-09 3i297E-09 1.941E-09 1.27tE-09 8.945E-10 6.629E-10 5.100E-10 1.643E-07 5.557E-08 2.853E-08 1.35&E-08 4.872E-09 2.416E-09 1.423E-09 9.31&E-10 6.555E-10 4.858E-10 3.743E-10 NNE 1.368E-07 4.627E-08 2.37&E-08 1.129E-08 4.057E-09 2 012E-09 1.185E-09 7.756E-10 5.458E-10 4.045E-10 3.117E-10 NE 1.119E-07 3.786E-08 1.944E-08 9.240E-09 3.319E-09 1.646E-09 9.492E-10 6.346E-10 4.466E-10 3.309E-10 2.550E-10 EhC 9.912E-08 3.152E-08 1.721E-08 8.182E-09 2.939E-09 1 458E-09 8.582E-10 5.620E-10 3.954E-10 2.930E-10 2.258E-10 E 8,609E-08 2.91tE-08 1.495E-08 7.106E-09 2.552E-09 1 266E-09 7.453E-10 4.880E-10 3.434E-10 2.545E-10 1.96tE-10 ESE 9.069E-08 3.067E-08 1.575E-08 7.48&E-09 2.689E-09 1 334E-09 7.852E-10 5.142E-10 3.618E-10 2.681E-10 2.066E-10 SE 1.225E-07 4.144E-08 2.128E-08 1.011E-08 3.633E-09 1.802E-09 1.061E-09 6.947E-10 4.888E-10 3.623E-10 2.792E-10 SSE 1.60lE-07 5.413E-08 2.779E-08 1.321E-08 4.746E-09 2 354E-09 1.386E-09 9.075E-10 6.384E-10 4.733E-10 3.647E-10 DIRECTION DISTANCES IN MILES F20M SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 S 1.917E-10 8.517E-11 5.160E-11 2.608E-11 1.578E-11 1.058E-Il 7.583E-12 5.694E-12 4.427E-12 3.537E-12 2.887E-12 SSW 2.715E-10 1.206E-10 7.305E-11 3.692E-11 2.235E-11 1.498E-11 1.074E-11 8.062E-12 6.268E-12 5.007E-12 4.087E-12 6W 3.865E-10 1.717E-10 1.040E-10 5.257E-11 3.182E-11 2 133E-11 1.529E-11 1 148E-11 8.925E-12 7.129E-12 5.819E-12 WSW 2.987E-10 1.327E-10 8.037E-11 4.062E-St 2.459E-11 1.640E-11 1.181E-11 8.870E-12 6.896E-12 5.509E-12 4.496E-12 c.
C)
W 1.591E-10 7.066E-11 4.280E-11 2.163E-11 1.309E-11 8.779E-12 6.29tE-12 4.724T-12 3.673E-12 2.934E-12 2.395E-12
"~ WNW 3.321E-10 1.475E-10 8.935E-11 4.516E-11 2.734E-11 1.833E-11 1.313E-11 9.86tE-12 7.447E-12 6.125E-12 4.999E-12 NW 3.880E-10 1.724E-10 1.044E-10 5.277E-It 3.194E-11 2.142E-11 1.534E-11 1.1522-11 8.959E-12 7.156E-12 5.841E-12 HNW 4.058E-10 1.803E-10 1.092E-10 5.520E-11 3.341E-11 2.240E-11 1.405E-11 1.205E-11 9.371E-12 7.486E-12 6.110E-12 N 2.974E-10 1.32tE-to 8.003E-11 4.045E-11 2.448E-11 1.642E-11 1.176E-11 8.832i-12 6.867E-12 5.486E-12 4.478E-12 NNE J 2.476E-10 1.100E-to 6.664E-11 3.368E-11 2.039E-1L 1 367E-11 9.794E-12 7.3545-12 5.718E-12 4.568E-12 3.728E-12 NE 2.026E-10 9.001E-11 5.452E-11 2.756E-11 1.668E-11 1 118E-11 8.013E-12 6.0171-12 4.479E-12 3.737E-12 3.050E-12 ENE 1.794E-10 7.970E-11 4.828E-11 2.440E-11 1.477E-11 9.902E-12 7.095E-12 5.328E-12 4.143E-12 3.309E-12 2.701E-12 E 1.55BE-10 6.92tE-11 4.193E-11 2.119E-11 1.283E-11 8.600E-12 6.162E-12 4.427E-12 3.598E-12 2.874E-12 2.34&E-12 ESE 1.44tE-10 7.292E-11 4.417E-11 2.233E-11 1.35tE-11 9.060E-12 4.492E-12 4.875E-12 3.790E-12 3.028E-12 2.471E-12 SE 2.218E-10 9.852E-11 5.968E-11 3.017E-11 1.826E-11 1.224E-11 8.772E-12 6.587E-12 5.12tE-12 4.091E-12 3.339E-12 SSE 2.897E-10 1.287E-10 7.797E-11 3.94tE-11 2.385E-11 1.599E-11 1.146E-11 8.404E-12 4.690E-12 5.344E-12 4.342E-12 sss*******setteess488888 RELATIVE DEPOSITION PER UNIT AREA (Mes-2) kV DOWNWIND SECTORS ******$s8$$$$$3884888888 SEGNENT BOUNDARIES IN MILES
> D1 ECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 rt FR!M SITE O
S 1.798E-08 3.683E-09 9.613E-10 4.3tBE-10 2.443E-10 9.393E-11 2.717E-11 1.077E-11 5.751E-12 3.560E-12 SS3 2.545E-08 5.214E-09 1.361E-09 6.113E-10 3.458E-10 1.330E-10 3.847E-11 1.525E-11 8.143E-12 5.040E-12
[ S3 3.624E-08 7.424E-09 1.930E-09 8.704E-10 4.924E-10 1.894E-10 5.478E-11 2.17tE-11 1.159E-11 7.176E-12 y CS3 2.800E-08 5.736E-09 1.497E-09 4.726E-10 3.805E-10 1.463E-10 4.233E-It 1.678E-11 8.959E-12 5.545E-12 re W 1.491E-08 3.055E-09 7.975E-10 3.582E-10 2.026E-10 7.792E-11 2.254E-11 0.934E-12 4.77tE-12 2.953E-12
,, WN3 3.114E-08 6.378E-09 1.445[-09 7.477E-10 4.230E-10 1.627E-10 4.706E-11 1.845E-11 9.960E-12 6.165E-12 c) NW 3.638E-08 7.452E-09 1.945E-09 8.737E-10 4.943E-10 1.90lE-10 5.499E-11 2.179E-11 1.164E-11 7.203E-12
,, NNW 3.005E-08 7.794E-09 2.035E-09 9.139E-10 5.170E-10 1.988E-10 5.752E-11 2.280E-l! 1.217E-11 7.535E-12 g) N 2.789E-08 5.712E-09 1.49tE-09 4.697E-10 3.789E-10 1.457E-10 4.215E-11 1.671E-11 8.92tE-12 5.522E-12
,s CZE 2.322E-08 4.756E-09 1.242E-09 5.576E-10 3.155E-10 1.213E-10 3.510E-11 1.39tE-11 7.428E-12 4.598E-12 e- NE 1.900E-08 3.891E-09 1.016E-09 4.563E-10 2.581E-10 9.926E-11 2.872E-11 1.138E-11 6.078E-12 3.762E-12 o ENE 1.682E-08 3.446E-09 8.995E-10 4.040E-10 2.285E-10 8.789E-11 2.543E-11 1.008E-11 5.38tt-12 3.33tE-12 Mb E 1.46tE-08 2.992E-09 7.812E-10 3.509E-10 1.985E-10 .7.633E-11 2.200E-11 8.752E-12 4.674E-12 2.893E-12
~ ESE 1.539E-08 3.153E-09 8.230E-10 3.696E-10 2.09tE-10 8.042E-It 2.326E-Il 9.220E-12 4.924E-12 3.048E-12
SE 2.080E-08 4.260E-09 1.It2E-09 4.994E-10 2.825E-10 1.087E-10 3.143E-11 1.246E-11 6.653E-12 4.118E-12 ,
SSE 2.717E-08 5.565E-09 1.453E-09 6.524E-10 3.69tE-10 1.419E-10 4.106E-11 1.627E-11 8.69tE-12 5.379E-12 '
ODCM TECHNICAL SPECIFICATIONS CROSS-REFERENCE (TABLE 13)
Tech Spec ODCM Dose Calculation Section Section Methodology 3.3.3.10 8.7 Determination of Alarm / Trip 3.11.1.1 Setpoints for Liquid 4.11.1.1.2 Monitors 3.3.3.11 8.13 Determination of Alarm / Trip
. 3.11.2.1 Setpoints for Gaseous 3.11.2.4 Monitors 4.11.2.4.1 3.11.1.1 8.6 Liquid Effluents 4.11.1.1.1 3.11.1.2 4.11.1.2 3.11.1.3 4.11.1.3.1 3.11.2.1 8.10 Gaseous Effluents 4.11.2.1.3 (Dose rate due to Noble Gases, 4.11.2.4.1 Radioiodines, Particulates, and Radionuclides with half-lives greater than 8 days.)
3.11.2.1 8.11 Noble Gases 3.11.2.2 4.11.2.2 3.11.2.3 8.12 Radiciodines, Particulates, and 4.11.2.3 Radionuclides with half-lives greater than 8 days 3.11.4 8.15 Total Dose 4.11.4.1 (40CFR190) 4.11.4.1 3.12.1 8.2 Radiological Environmental 4.12.1 Monitoring 3.12.3 8.3 Interlaboratory Comparison Program 4.12.3 HP-1-230, Rev.4 102 Attachment 10.20 (1 of 1) w_
T l
LOUISI ANA / 44 Oe-O~Oe raser . ao .Ox.oo.
2OWER & LIGHT / New OALeANS LOUSMNA 70174-0008 G (504)388-2345
$SISNSYSN August 29, 1985 W3P85-1466 A4.05 Mr. Robert D. Martin Regional Administrator, Region IV j hh] }{\//F7f li.S. Nuclear Regulatory Commission t
611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 i MCOg ,
e l
Dear Mr. Martin:
j
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semiannual Radioactive Effluent Release Report Enclosed is the subject report on effluent releases which covers the period of March 4 (initial criticality) to June 30, 1985. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-1117) of Appendix A to Facility Operating License No. NPF-38 tnd pursuant to 10 CFR 50.36a(a)(2).
Very truly yours, K.W. Cook Nuclear Support & Licensing Manager KWC:CEW:sms Enclosure cc (w/ enclosure): NRC, Director, Office of I&E Document Control Desk, NRC, Washington, D.C.
cc (w/o enclosure): G.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson
/
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