ML20125A178
| ML20125A178 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/17/2019 |
| From: | Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20125A185 | List:
|
| References | |
| L-20-137 | |
| Download: ML20125A178 (131) | |
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RTL #A9.621B Beaver Valley Power Station Unit 1/2 l/2-0DC-2.02 ODCM: GASEOUS EFFLUENTS Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 11 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 07/17/19
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2 of 131 TABLE OF CONTENTS 1.0 PURPOSE......................................................................................................................................... 4 2.0 SCOPE.........................................................,..................................................................... ;............... 4
3.0 REFERENCES
AND COMMITMENTS........................................... :............................................. 4 3.1 References............................................................................................................................................................................................... 4 32 Corrunfunents......................................................................................................................................................................................... 7 4.0 RECORDS AND FORMS................................................................................................................ 7 4.1 Records*.................................................................................................................................................................................................... 7 42 Fonns.... *.............................................................................................................................................................. -................................... 7 5.0 PRECAUTIONS AND LIMITATIONS.......................................................................................... 7 5.1 Precautions............................................................................................................................................................................................... 7 52 Limitations............................................................................................................................................................................................... 8 6.0 ACCEPTANCE CRITERIA............................................................................................................. 9 7.0 PREREQUISITES..............................................................,............................................................. 9 8.0 PROCEDURE................................................................................................................................. 10 8.1 Alann Setpoints.................................................................................................................................................................................... 10 8.1.1 BV-1 Monitor Alarm Setpoint Determination..................................................... 10 8.1.2 BV-2 Monitor Alarm Setpoint Determination....... :............................................. 19 8.1.3 BV-1/2 Monitor 1Alarm Setpoint Determination.................................................. 29 82 Compliance Wrth 10 CFR20 Dose Rate Limits (ODCM CONIROL 3.112.1).......................................................... 35 8.2.1 Dose Rate Due To Noble Gases.......................................................................... 35 8.2.2 Dose Rate Due To Radioiodines And Particulates.............................................. 43 83 ComplianceWrthlOCFR50DoseLimits(ODCMCON1ROLS3.1122And3.112.3)(Gaseous)................... 46 8.3.1 Dose Due To Noble Gases................................................................................... 47 8.3.2 Dose Due To Radioiodines And Particulates...................................................... 54 8.4 Gaseous Radvvaste System............................................................................................................................................................... 70 8.4.1 BV-1 Gaseous Radwaste System Components................................................... 70 8.4.2 BV-2 Gaseous Radwaste System Components................................................... 71
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ATTACHMENT A ATTACHMENT B ATTACHMENT C ATTACHMENTD ATTACHMENT E ATTACHMENT F ATTACHMENTG ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENTK ATTACHMENTL ATTACHMENTM ATTACHMENTN ATTACHMENT 0 ATTACHMENTP ATTACHMENT Q 11 3 of 131 TABLE OF CONTENTS GASEOUS SOURCE TERM................ :............................................................. 73 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES................ 75 DELETED............................................................................................................ 77 RADIONUCLIDE MIX....................................................................................... 78 DISTANCES TO RELEASE POINTS................................................................ 80 0-5 MILEDISPERSIONPARAMETERS............*............................................. 81 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS........................ 88 ORGAN DOSE PARAMETERS........................................................................ 90 MODES OF GASEOUS RELEASE... -................................................................ 91 P&I ORGAN DOSE FACTORS......................................................................... 92 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)..... 111 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)................................................................... -................. :............... 118 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES).................................................................................................... 125 BATCH RELEASE DISPERSION PARAMETERS (0-5 MILES)................ 128 GASEOUS RAD WASTE SYSTEM................................................................. 129
-BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS..................... 130 SITE BOUNDARY FOR GASEOUS EFFLUENTS........................................ 131
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4 of T ~ T 1.0 PURPOSE 1.1 This procedure provides the methodology to calculate dose, dose rates, and alarm setpoints from gaseous effluents in accordance with the requirements of Beaver Valley Technical 2.0 2.1 3.0 3.1 Specifications [TS] 5.5.2.
1.1.1 1.1.2 1.1.3 1.1.4 1.1.5 Gaseous effluent monitor alarm setpoints [TSJ 5.5.2.a Gaseous effluent dose rate calculations [TS] 5.5.2.g Gaseous effluent dose calculations [TS] 5.5.2.g, [TS] 5.5.2.h, [TS] 5.5.2.i Gaseous Radwaste Treatment System [TS] 5.5.2.f Site Boundary used for gaseous effluents SCOPE This procedure is applicable to gaseous effluents at Beaver Valley Power Station.
REFERENCES AND COMMITMENTS References 3.1.1 References for BV-1 Gaseous Effluent Monitor Setpoints 3.1.1.1 3.1.1.2 3.1.1.3 3.1.1.4 3.1.1.5 3.1.1.6 3.1.1.7 3.1.1.8 Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412; Table 2.1-3 Beaver Valley Power Station, Unit 2 UFSAR; Table 11.3-1 BVPS Specification No. BVS 414, Table V Nuclide Data,; Table 1 and Figure 1, Table 3, and Figure 2, May 30, 1974 Calculation Package No. ERS-SFL-85-031, Unit 1 Gaseous Effluent Monitor Efficiency Data Calculation Package No. ERS-HHM-87-014, Unit I/Unit 2 ODCM Gaseous Alarm Setpoint Determinations Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification LetterNDISHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment V 8:cuum Pumps
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5 of 131 3.1.2 References for BV-2 Gaseous Effluent Monitor Setpoints 3.1.2.1 3.1.2.2 3.1.2.3 3.1.2.4 3.1.2.5 Calculation Package No. ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies Calculation Package No. ERS-HHM-87-014, Unit I/Unit 2 ODCM Gaseous Alarm Setpoint Determinations Beaver Valley Power Station, Unit 2 UFSAR; Table 11.3-2 Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.3 References used in other sections of this procedure 3.1.3.1 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.1.3.3 NUREG-0324; XOQDOQ Program for the Meteorological Evaluation of Routine Releases at Nucle~r Power Stations, September 1977 3.1.3.4 NUREG-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluent~ form PWR's Revision 0.
3.1.3.5 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Release of Reactor Effluents For the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I, March 1976.
3.1.3.6 Regulatory Guide 1.109, Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose oflmplementing Appendix I, April 1977 3.1.3. 7 NUREG-0172, Age - Specific Radiation Dose Commitment Factors for a one-year Chronic Intake 3.1.3.8 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual
- 3.1.3.9 1/2-ADM-0100, Procedure Writers Guide 3.1.3.10 NOP-SS-3001, Procedure Review and Approval
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6 of Bl 3.1.3.11 CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit 1 Containment Vacuum Pump Source-Term in ODCM procedure l/2-0DC-2.02, Attachment A, Table 2.1-la.
3.1.3.12 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.
CA-16, Revise procedure l/2-0DC-2.02 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.
3.1.3.13 Unit 1 Technical Specification Amendment No. 275 (LAR lA-302) to License No.
DPR-66. This amendment to the Unit I license was approved by the NRC on July 19, 2006.-
3.1.3.14 Vendor Calculation Package No. 8700-UR(B)-223, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternative Source Terms on the Alarm Setpoints for the Radiation Monitors at Unit 1.
3.1.3.15 Engineering Change Package No. ECP-04-0440; Extended Power Uprate.
3.1.3.16 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure l/2-0DC-2.02 to update the alarm setpoints of gaseous effluent radiation monitor for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275.
3.1.3.17 MELCOR Accident Consequence Code System for the Calculation of the Health and Economic Consequences of accidental Atmospheric Radiological Releases (MACCS2 V.1.12), Oak Ridge National Laboratory.
3.1.3.18 Federal Guidance Report No. 11: Limiting Values of Radionuclide Intake And Air Concentration and Dose Conversion Factors For Inhalation, Submersion, and Ingestion, September 1988.
3.1.3.19 Federal Guidance Report No. 12: External Exposure to Radionuclides in Air, Water, and Soil, September 1993.
3.1.3.20 L. R. McKay (Ed.), A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment (ORNL-4992), Oak Ridge National Laboratory, 1975.
3.1.3.21 CR 10-85877, Selertium-75 (Se-75) discharge via Ul/U2 Process Vent. CA-02 revises ODCM procedure l/2-0DC-2.02 to include dosefactors for Se-75.
3.1.3.22 Technical Evaluation Package ERS-LMR-12-001, ODCM Pit and R values for Carbon-14.
3.1.3.23 Notification 600727275 and CR #2012-17177, Revise l/2-0DC-2.02, Gaseous Effluents, with the R values for Sb-126.
3.1.3.24 Notification 600737534 Item #4, Revise ODCM for Carbon-14.
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11 7 ofnl 3.1.3.25 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.
3.1.3.26 Calculation Package No. ER~-ATL-83-027; Liquid Waste Dose Factor Calculation for Yz-ENV-05.06 3.1.3.27 Calculation Package No. ERS-ATL-89-014; Verification/Validation of ODCM Values 3.1.3.28 Calculation Package No. ERS-LMR-15-006; Additional Effluent Dose Factors 3.1.3.29 Engineering Change Package No. ECP..,.16-0026; Pump/Motor Assembly Replacement 3.1.3.30 Engineering Change Package No. ECP-16-0113; BVl Process Radiation Monitoring System Replacement 3.l,3.31 Engineering Change Package No. ECP-18-0043; BVl Radiation Monitoring System Upgrade Phase 2 3.1.3.32 EPRI document Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" 3.1.3.33 Engineering Change Package No. ECP-13-0829; Engineering Change Package No.
ECP-13-0829: Install Blank-Off Flanges on the Inlet and Outlet of Unit 2 Condensate Polishing System 3.2 Commitments 3.2.1 Beaver Valley Technical Specifications: [TS] 5.5.2, Radioactive Effluent Controls Program.
4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 Precautions 5.1.1 None.
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8 of 131 ODCM: GASEOUS EFFLUENTS 5.2 Limitations 5.2.1 Offsite Dose Calculation Manual (ODCM) controls applicable to dose rate apply to the site. The site,dose rate is calculated by summing the releases from both units.
5.2.2 ODCM controls applicable to accumulated dose apply individually to each unit.
5.2.3 Releases at the Beaver Valley site are characterized as Ground Level or Elevated in nature.
5.2.3.1 5.2.3.2 Ground Level releases are attributed to the specific unit for which the release occurs. Determination of site dose rate and dose is assigned to the specific unit.
Elevated releases are attributed to both units because they originate, by design from a shared radwaste system. Elevated releases are discharged from a common release point, the Process Vent, at the top of the BV-1 cooling tower.
5.2.4 Dose from continuous and batch (Gas Waste Storage Tanks) releases at BV-1 and BV-2 via the shared radwaste system (Process Vent) are normally attributed equally to the units. Containment purge through the Process* Vent is attributed to the specific unit for which it originates. Continuous and batch releases via non-shared tadwaste systems shall be attributed to the specific unit for which it originates.
5.2.5 A difference in alarm setpoint terminology presentations for the radiation monitoring systems ofBV-1 and BV-2 is described as follows:
5.2.5.1 5.2.5.2 5.2.5.3 HIGH and HIGH-HIGH terminology are used for the BV-1 Victoreen monitors, ALERT and HIGH terminology are used for the BV-1 Mirion PING monitors and the BV-2 monitors.
BV-1 alarm setpoints are expressed in counts per minute (cpm) and BV-2 alarm setpoints are expressed in microcurie per cubic centimeters (uCi/cc). The difference is due to BV-2 software which applies a conversion factor to the raw data ( cpm) to convert units to uCi/cc. Note that the uCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the*.conversion factors. Therefore, BV-2 setpoints determined on analysis prior to release will be correct for properly controlling dose rate, but the indicated uCi/cc value may differ from the actual value.
BV-1 and BV-2 effluent monitors specified in this procedure have Upper Alarm Setpoints established at sixty (60) percent of the site limit and Lower Alarm Setpoints established at thirty (30) percent of the site limit.
5.2.6 Releases are characterized as batch or continuous in nature.
5.2.6.1 Batch refers to releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment purges, and venting of systems or components with infrequent use.
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9 of 131 5.2.6.2 5.2.6.3 5.2.6.4 11 Batch releases may occur due to operational variations which result in radioactive releases greater than fifty (50) % of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of five-hundred (500) hours or less in a calendar year, but not more than one-hundred (150) hours in any quarter.
The batch relative concentration value has been calculated in accordance with the guidelines provided in NUREG-0324(3.1.33) for short-term release.
If a batch and continuous release occur simultaneously from the same vent path, then use the lowest setpoint obtained as determined in Sections 8.1.1.1 through 8.1.3.2.
5.2.7 This procedure also contains information that was previously contained in Section 5 of the previous BV-1 and BV-2 Offsite Dose Calculation Manual.
5.2.7.l 5.2.7.2 In regards to this, the site boundary for gaseous effluents was included in this procedure.
The Site Boundary for Gaseous Effluents is shown in ATTACHMENT P Figure 5-1.
6.0 ACCEPTANCE CRITERIA 6.1 Changes to this procedure shall contain sufficient justification that the change will maintain the level ofradioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculation. <3.u.2>
6.1.1
- Changes to this procedure shall be prepared in accordance with 1/2-ADM-0100, PROCEDURE WRITER'S GUIDE <3.ns) and 1/2-ADM-1640, CONTROL OF THE OFFSITE DOSE CALCULATION MANUAL.<3.u.7) 6.1.2 Changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001, PROCEDURE REVIEW AND APPROVAL <3.1 3.9) and 1/2-ADM-1640.
(3.1.3.7) 7.0 PREREQUISITES 7.1 None.
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10 of 131 8.0 8.1 PROCEDURE Alarm Setpoints 8.1.1 BV:..l Monitor Alarm Setpoint Determination ODCM CONTROL 3.11.2.1 require that the dose rate in unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site shall be limited to
- S 500 mrem/yr to the total body and to ::S 3000 mrem/yr to the skin.
This section describes the methodology used to maintain the release of noble gas radionuclides within ODCM CONTROL 3.11.2.1 for the site, and determines monitor setpoints for BV-1.
The methodologies described in Section 8.1.1.2, 8.1.2.2, and 8.1.3.2 provide an alternate means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release.
Control of the site dose rate limit due to noble gases is shown in the following Table. Dose rate control is exercised through a total of seven (7) effluent stream monitors, of which three (3) are located at BV-1 (alternates exists for these monitors), and four (4) are located at BV-2. As previously noted, BV-1 and BV-2 elevated releases are via the PV-1/2 Process Vent.
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11 11 of 131 Monitor Setpoint Specifications Based On Fraction Of Site Limit UNIT RELEASE POINT MONITOR NO.
FRACTION OF SITE LIMITING DOSE RATE (VV-1) Unit 1, Auxiliary Building Vent Pri.: RM-lVS-109 LRNG or Upper Alarm 60%(HIGH)
Alt.: RM-IVS-101B 60% (HIGH-HIGH)
(CV-1) Unit 1, Rx Containment/SLCRS Vent Pri.: RM-IVS-110 LRNG or 60% (HIGH)
Alt.: RM-1VS-107B 60% (HIGH-HIGH)
(PV-1/2), Unit 1/2, Gaseous Waste/Process Vent Pri.: RM-IGW-108B or 60% (HIGH-HIGH)
Alt.: RM-IGW-109 LRNG 60% (HIGH)
(CV-2), Unit 2, SLCRS Filtered Pathway 2HVS-RQ109E 60% (HIGH)
(VV-2), Unit 2, SLCRS Unfiltered Pathway 2HVS-RQ101B 60% (HIGH)
(WV-2), Unit 2, Waste Gas Storage Vault Vent 2RMQ-RQ303B 60% (HIGH)
(DV-2), Unit 2, Decontamination Building Vent 2RMQ-RQ301B 60% (HIGH)
Lower Alarm 30%(ALERT) 30%(ALERT) 30%(ALERT) 30%(HIGH) 30% (HIGH) 30%(ALERT) 30%(ALERT) 30%(ALERT) 30%(ALERT) 30%(ALERT)
With the monitor setpoints based on fractions of the site limit as defined above, the following criteria may be applied to determine that the dose rate due to noble gas released from the site complies with ODCM CONTROL 3.11.2.1:
The site dose rate is thirty (30) % of the site dose rate limit when any monitor is indicating a Lower Alarm.
The site dose rate is sixty (60) % of the site dose rate limit when any two monitors are indicating Lower Alarms.
The site dose rate is sixty (60) % of the site dose rate limit when any monitor is indicating an Upper Alarm.
The site dose rate is ninety (90) % pf the site dose rate limit when any monitor is indicating an Upper Alam1 and any other monitor is indicating a Lower Alarm.
,l
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12 of 131 8.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For VV-1 and CV-1 Ground Releases The table below gives the calculated monitor count rate above background (CR), in ncpm, and provides the equivalent monitor indication (DV) in net uCi/sec associated with the most limiting site dose rate limit (i.e.; 500 mrem/yr Total Body or 3000 mrem/yr skin). The monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each vent and operational condition shall be as follows:
BVI ALARM SETPOINTS FOR GROUND RELEASES NET ABOVE BACKGROUND 60%
30%
(P) PRIMARY* MONITOR SITE SITE (A) ALTERNATE MONITOR LIMIT LIMIT UPPER LOWER CR DV ALARM ALARM
- Continuous Release Via The BV-(P) RM-lVS-109 LRNGO) 6.25 2640
~ 1580
~792 1 Auxiliary Building Vent (VV-1) cps
µCi/sec
µCi/sec
µCi/sec (A) RM-IVS-IOIB 4080
~2450
~ 1220 cpm cpm Cpm
- Batch Release Of Containment (P) RM-lVS-109 LRNQO) 6.36 1050
~ 633
~ 316 Purge Via The BV-1 Auxiliary cps
µCi/sec
µCi/sec
µCi/sec Building Vent (VV-1)
(A) RM-1VS-10IB 1490
~2620
~ 1310 cpm cpm Cpm
- Continuous Release Via The BV-(P) RM-1 VS-110 LRNG<1) 13.9 3790
~2270
~ 1140 1 Rx Containment/SLCRS Vent cps
µCi/sec
µCi/sec
µCi/sec (CV-1)
(A) RM-I VS-107B 6580
~ 3950
~ 1970 cpm cpm Cpm
- Batch Release Of Containment (P) RM-lVS-110 LRNG<1) 27.4 1140
~682
~ 341 Purge Via The BV-1 Rx cps
µCi/sec
µCi/sec
µCi/sec Containment/SLCRS Vent (A) RM-1VS-I07B 13,000
~7790
~ 3890 (CV-1) cpm cpm Cpm
- IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized.
(I)Each Mirion PING Monitor skid is equipped with a low range monitor (LRNG) and a high range monitor (HRNG). The low range monitor has three setpoints: ALERT, HIGH, and HIGH-HIGH. The HIGH-HIGH setpoint will be used to swap from the low range monitor to the high range monitor.
The setpoints were determined using the following conditions and information:
Source terms given in ATTACHMENT A Table 2.1-la. The gaseous source terms were derived from Stone & Webster computer code GASlBB (similar to NUREG-0017),(3.1.3.4) and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-la does not include particulates and*
iodines, which are not used in site noble gas dose rate calculations.
Onsite meteorological data for the period January 1, 1976 through December 31, 1980.
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11 13 nf 131 Discharge flow rate of 62,000 cfin for a VV-1 Continuous Release.
Discharge flow rate of 92,000 cfin for a VV-1 Batch Release of Containment Purge.
This is comprised of 30,000 cfin from the containment purge plus 62;000 cfm for VV-1.
Discharge flow rate of 49,300 cfin for a CV-I Continuous Release.
Discharge flow rate of 56,800 cfin for a CV-I Batch Release of Containment Purge.
This is comprised of 7,500 cfin from the containment purge plus 49,300 cfm for CV-1.
Information listed under References for BV-1 Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 8.1.1.1.1 through 8.1.1.1. 7 was used to derive the monitor setpoints for the following operational conditions:
Continuous release via VV-1.
Continuous release via CV-I.
Batch.. release ofBV-1 Containment Purge via VV-1.
Batch release ofBV-1 Containment Purge via CV-1.
8.1.1.1.1 BV-1 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-la.
The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by:
[2.1(1)-1]
where:
Ai = The total radioactivity or radioactivity concentration of noble gas
- radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la.
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14 of 131 8.1.1.1.2 BV-1 Maximum Acceptable Release Rate (Whole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by:
500 Ot = (X/Q) L i
[2.1(1)-2]
where:
(X/Q)vv
=
The highest calculated annual average relative concentration of effluents released via VV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-5.
(X/q)vv
=
l.03E-4 sec/m3 for continuous releases.
The highest calculated short term relative concentration of effluents released via VV-1 for any*area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-36.
=
3.32E-4 sec/m3 for batch release of containment purge.
(X/Q)cv
=
The highest calculated annual average relative concentration (X/q)cv of effluents released via CV-1 for any area at or beyond the
~nrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-4.
=
9.24E-5 sec/m3 for continuous releases.
=
The highest calculated short term relative concentration of effluents released via C'V_-1 for any area at or beyond the unrestricted area boundary for any sectors (sec/m3) from ATTACHMENT M Table 2.3-35.
=
3.08E-4 sec/m3 for batch release of containment purge.
Ki
=
The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
Si
=
From equation [2.1 (1 )-1] above.
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8.1.1.1.3 8.1.1.1.4 8.1.1.1.5 11 1 'i of n1 BV-1 Maximum Acceptable Release Rate (Skin Exposure)
Qt was also determined based upon the skin exposure limit by:
Qt=
3000 (X/Q)L (Li+ 1.lMJ Si
[2.1(1)-3]
1 where:
1.1 (X/Q)
I
=
The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
=
The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).
=
Same as in Section 8.1.1.1.2.
BV-1 Maximum Acceptable Release Rate andividual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by:
[2.1 (1 )-4]
NOTE: Use the lower of the Qt values obtained in Section 8.1.1.1.2 and 8.1.1.1.3.
BV-1 Maximum Acceptable Concentrations Undividual Radionuclide)
The maximum acceptable radioactivity conce_ntration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide "i" in the gaseous effluent was determined by:
Ci = 2.12E-3 Qi /
F where:
[2.1(1)-5]
F
= The maximum acceptable effluent flow rate at the point of release ( cfm) as listed in Section 8.1.1.1.
2.12E-3 =
Unit conversion factor (60 sec/minx 3.53E-5 ft3/cc).
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16 of n1 8.1.1.1.6 8.1.1.1.7 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm for Victoreen Monitors and ncps for Mirian Monitors) above background attributed to the noble gas radionuclide.
CR was determined by:
CR=}:CR i
where:
[2.1(1)-6)]
Ei = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc for Victoreen or cps/uCi/cc for Mirian) from ATTACHMENTB Table 2.1-2a.
BV-1 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:
The Victoreen monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by:
HHSP = 0.60 x CR
[2.1(1)-7]
The Victoreen monitor HIGH Alarm Setpoint above background (ncpm) was determined by:
HSP = 0.30 x CR
[2.1(1)-8]
NOTE: The values 0.60 for the HHSP and 0.30 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units.
- . The Mirian monitor HIGH Alarm Setpoint above background (uCi/sec) was determined by:
HSP = 0.60 x Qt
[2.1(1)-9]
The Mirian monitor ALERT Alarm Setpoint above background (uCi/sec) was determined by:
ASP = 0.30 x Qt
[2.1(1)-10]
NOTE: Use the lo,wer of the Q1 values obtained in Section 8.1.1.1.2 and 8.1.1.1.3.
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8.1.1.2 8.1.1.2.1 11 17 of 131 BV-1 Setpoint Determination Based On Analysis Prior To Release For VV-1 and CV-1 Ground Releases When the setpoints established using "the calculated mix" for ground releases do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Step 8.1.1.1. In this case, the results of sample analysis are used to determine the source term "mix." This calculational method applies to gaseous releases via VV-1 and CV-1 when determining the setpoint for the maximum acceptable discharge flow rate and the assqciated HIGH-HIGH Alarm Setpoint based on this flow rate during the following operational conditions:
Batch release of Containment Purge via VV-1.
Batch release of Containment Pqrge via CV-1.
BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-1 and CV-1 during
/ purging is determined as follows:
The maximum acceptable gaseous discharge flow rate (f) from VV-1 and CV-1 ( c:fin) during purging based upon the whole body exposure limit is calculated by:
1.06 ST f = (X/q) L Ki Ci i
[2.1 (1 )-17]
where:
1.06
= 500 mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit 2.12E-3
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
S
= Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 8.1.1.
T
= Maximum value for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged *over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16). <3. 1.1.6)
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1 R of 131 (Xlq)vv = The highest calculated short term relative concentration of effluents released via VV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-36.
= 3.32E-4 sec/m3 (X/q)cv
= The highest calculated short term relative concentration of effluents released via CV-1 for areas at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-3 7.
= 3.08E-4 sec/m3 Ki
= The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
Ci
= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36 ST f=--------
(X/q) L (Li + 1.1Mi) Ci i
where:
6.36 = 3000 mrem/yr x 2.12E-3 3000 mrem/yr = dose rate limit 2.12E-3
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
[2.1 (1 )-18]
Li
= The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 1
2.2-U.
Mi
= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
(X/q) = Same as above.
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19 of 131 8.1.1.2.2 1 I The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate ( cfln) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
BV-1 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
The calculated Victoreen monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attributed to noble gas radionuclides is determined by:
f L Ci Ei HHSP =
iF' where:
[2.1(1)-19]
f
= The maximum acceptable gaseous discharge flow rate ( cfln) determined in Section 8.1.1.2.1.
F'
= The maximum actual or design effluent flow rate ( cfm) at the point of release.
= 92,000 cfm for VV-1
= 56,800 cfm for CV-1 Ci
= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
Ei
= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.
When a Victoreen monitor HIGH-HIGH set point has been calculated according to this section, the monitor HIGH Alarm Setpoint above background (ncpm) is determined as follows:
HSP = HHSP x 0.5
[2.1 (1)-20]
8.1.2 BV-2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determinations.
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?O of n1 8.1.2.1 BV-2 Setpoint Determination Based On A Calculated Mix For VV-2, CV-2, DV-2 and WV-2 Ground Releases.
The table below gives the calculated monitor count rate above background (CR) in ncpm, and provides the equivalent monitor indication (DV) in net uCi/cc associated with the most limiting site dose rate limit (i.e., 500 mrem/yr Total Body or 3000 mrem/yr Skin). The HIGH alarm setpoint (HSP) in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCi/cc above background for each vent and operational condition shall be as follows:
BV2 ALARM SETPOINTS FOR GROUND RELEASES uCi/cc ABOVE BACKGROUND (unless otherwise specified) 60%
30%
SITE SITE LIMIT LIMIT CR UPPER LOWER MONITOR ncpm DV ALARM ALARM Continuous Release Via The BV-2 2HVS-RQ101B 8260 3.0lE-4
- 5: l.8IE-4 ::; 9.04E-5 SLCRS Unfiltered Pathway (VV-2)
Batch Release Of Containment Purge 2HVS-RQ101B 2020 7.39E-5
- 4.43E-5
- 5: 2.22E-5 Via The BV-2 SLCRS Unfiltered Pathway (VV-2)
Continuous Release Via The BV-2 2HVS-RQ109B 4320 2940
- 1770
- 5: 883 SLCRS Filtered Pathway (CV-2)
µCi/sec
µCi/sec
µCi/sec Batch Release Of Containment Purge 2HVS-RQ109B 16,400 1130
- 5: 676
- 338 Via The BV-2 SLCRS Filtered Pathway
µCi/sec
µCi/sec
µCi/sec (CV-2)
Continuous Release Via The BV-2 2RMQ-RQ301B 56,600 3.lSE-3
- 5: l.89E-3 :5: 9.44E-4 Decontamination Building Vent (DV-2)
Continuous Release Via The BV-2 2RMQ-RQ303B 912,000 2.58E-2
- 5: l.55E-2 ::; 7.74E-3 Waste Gas Storage Vault Vent (WV-2)
The setpoints were determined using the following conditions and information:
The Decontamination Building ventilation exhaust is not expected to be radioactive. However, for purposes of determining an alarm setpoint, it is conservatively assumed that Xe-133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits.
I~
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11 21 of 111
- The Waste Gas Storage Vault ventilation exhaust is also not normally radioactive. However, the monitor alarm setpoint is based on the assumption that the ventilation: exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the waste gas storage vault. This spectrum is listed in ATTACHMENT A Table 2.1-lb under Gaseous Waste System.
- Onsite meteorological data for the period January 1, 197 6 through December 31, 1980.
- Discharge flow rate of 23,700 cfm for a VV-2 Continuous Release.
- Discharge flow rate of 53,700 cfm for a VV-2 Batch Release of Containment Purge. This is comprised of 30,000 cfm from the containment purge plus 23,700 cfm from the CV-2.
- Discharge flow rate of 59,000 cfm for a CV-2 Continuous Release.
- Discharge flow rate of 66,500 cfm for a CV-2 Batch Release of Containment Purge. This is comprised of 7,500 cfm from the containment purge plus 51,500 cfm from CV-2.
- Discharge flow rate of 12,400 cfm for DV-2 Continuous Release.
- Discharge flow rate of2,000 cfm for WV-2 Continuous Release.
- Information listed under References for BV-2 Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 8.1.2.1.1 through 8.1.2.1.7 was used to derive the alarm setpoints for the following operational conditions:
- Continuous release via VV-2.
- Continuous release via CV-2.
- Batch release ofBV-2 Containment Purge via VV-2.
- Batch release ofBV-2 Containment Purge via CV-2.
- Continuous release via DV-2.
I
- Continuous release via WV-2.
I
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8.1.2.1.1 8.1.2.1.2 11
?,2 of n1 BV-2 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-lb.
The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by:
[2.1(2)-1]
where:
Ai = The radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent (for VV-2, CV-2 and WV-2) is from ATTACHMENT A Table 2.1-lb. However, SINCE releases via DV-2 do not have a valid source term mix, THEN the noble gas radioactivity concentration is assumed to be Xe-133.
BV-2 Maximum Acceptable Release Rate (Whole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by:
500 Qt= (X/Q) 'f.Ki Si i
where:
[2.1(2)-2]
(X/Q)vv = The highest calculated annual average relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-5.
=
1.03E-4 sec/m3 for continuous releases.
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8.1.2.1.3 11 23 of 131 (X/q)vv = The short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-36.
= 3.32E-4 sec/m3 for batch release of containment purge.
(X/Q)cv = The highest calculated annual average relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-4.
= 9.24E-5 sec/m3 for continuous releases.
(X/q)cv = The short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-35.
= 3.08E-4 sec/m3 for batch release of containment purge.
(X/Q)dv = The highest calculated annual average relative concentration of effluents released via DV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-8.
= 9.24E-5 sec/m3 for continuous releases.
(X/Q)wv = The highest calculated annual average relative concentration of effluents released via WV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENTF Table 2.2-9.
= 9.24E-5 sec/m3 for continuous releases.
Ki
=
- The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m3)from ATTACHMENT G Table 2.2-11.
Si
= From equation [2.1 (2)-1].
BV-2 Maximum Acceptable Release Rate {Skin Exposure)
Qt was also determined based upon the skin exposure limit by:
[2.1(2)-3]
,J
~
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?4 of 131 8.1.2.1.4 8.1.2.1.5 where:
Li
= The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
Mi
= The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
1.1
= The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).
(X/Q)
= Same as in Section 8.1.2.1.2.
BV-2 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each noble gas radionuclide in the gaseous effluent was determined by:
[2.1(2)-4]
NOTE: Use the lower of the Qi values obtained in Section 8.1.2.1.2 and 8.1.2.1.3.
BV-2 Maximum Acceptable Concentrations Undividual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide in the gaseous effluent was determined by:
Ci = 2.12E-3 Qi F
where:
[2.1 (2)-5]
F
= The maximum acceptable effluent flow rate at the point of release
( cfm) as listed in Section 8.1.2.1.
2.12E-3 = Unit conversion factor (60 sec/minx 3.53E-5 ft3/cc).
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11
?." of n1 8.1.2.1.6 BV-2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (CR) was determined by:
CR=~C-E*
~ l l
[2.1(2)-6)]
i where:
Ei
= The detection efficiency of the monitor for noble gas radionuclide "i"
( cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b.
8.1.2.1.7 BV-2 Monitor Setpoints 8.1.2.2 The monitor alarm setpoints above background were determined as follows:
The monitor HIGH Alarm Setpoint above background (uCi/cc) was determined by:
0.60 xCR HSP= Ei ave
[2.1(2)-7]
where; Eiave
= The CR of equation [2.1(2)-6] divided by the sum of the Ci for the respective mix.
The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by:
0.30 x CR ASP=
Ei ave
[2.1(2)-8]
BV-2 Setpoint Determination Based On Analysis Prior To Release for VV-2 and CV-2 Ground Releases When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Section 8.1.2.1. In this case, the results of sample analysis are used to determine the appropriate nuclide mix. This calculational method applies when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH Alarm Setpoint based on respective vent flow rate during the following operational conditions:
Batch release of Containment Purge via VV-2.
Batch release of Containment Purge via CV-2.
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8.1.2.2.1 11
'Jt:. of Bl BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-2 or CV-2 during purging is determined as follows:
The maximum acceptable gaseous discharge flow rate (t) from VV-2 or CV-2 (cfin) during purging based upon the whole body exposure limit is calculated by:
1.06 ST
[2.1(2)-17]
where:
1.06
= 500 mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit, whole body exposure 2.12E-3
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
S
= Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.2.
T
= Maximum value for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16).<3.1.2.4)
(X/q)vv = The highest calculated short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-36.
= 3.32E-4 sec/m3 (X/q)cv = The highest calculated short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT M Table 2.3-37.
= 3.08E-4 sec/m3 Ki
= The total whole body dose factor due to gamma emissions fro.m noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
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27 of 131 11 Ci
= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
\\
The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36 ST f=--------
(X/q) L (Li + 1.1Mi) Ci i
where:
6.36 = 3000 mrem/yr x 2.12E-3 3000 mrem/yr = dose rate limit, skin exposure 2.12E-3
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
[2.1(2)-18]
Li
= The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
Mi
= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
1.1
= The ratio of the tissue to air absorption coefficients over the ~nergy range of the photons of interest, (mrem/mrad).
(X/q) = Same as above.
The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate ( cfin) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
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28 of 131 8.1.2.2.2 BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
The calculated monitor HIGH Alarm Setpoint above background (net uCi/cc) attributed to the noble gas radionuclides is determined by:
HSP= F'E*
i ave
[2.1 (2)-19]
where:
f
= The maximum acceptable containment purge flow rate (cfm) determined in Section 8.1.2.2.1.
F'
= The maximum actual or design effluent flow rate ( cfm) at the point of release.
= 53,700 cfm for VV-2
= 59,000 cfm for CV-2 Ci
= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
Ei
= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2. l-2b.
Ei ave
= The CR of equation [2.1 (2)-6] divided by the sum of the Ci for the respective mix.
NOTE:
To enable maintaining a constant conversion factor from cpm to uCi/cc in the Digital Radiation Monitoring System software, the "calculated mix" is used rather than the analysis mix to calculate Ei ave above. This does not cause any change in the function of the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.
When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:
ASP = HSP x 0.5
[2.1 (2)-20]
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11
'JQ of 131 8.1.3 BV-1/2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determination.
8.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix For PV-1/2 Elevated Releases The calculated monitor count rate above background (CR), in ncpm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are shown in the following Table:
BV-1/i ALARM SETPOINTS FOR GROUND RELEASES
- Continuous Release (P) PRIMARY* MONITOR (A) ALTERNATE MONITOR (P)RM-IGW-108B (A)RM-lGW-109 LRNG<1>
- Batch Release OfBV-1 Decay (P)RM-IGW-108B Tanks.or BV-2 Storage Tanks (A)RM-IGW-109 LRNG<1>
ncpm ABOVE BACKGROUND (unless otherwise specified)
CR 3.49E7 cpm l.07E5 cps 3.93E5 cpm.
3.54E4.
l.09E6
µCi/sec 2.25E5 60%
30%
SITE' SITE LIMIT LIMIT UPPER LOWER ALARM. ALARM
$ 3.60E5
~ l.20E5 cpm cpm
~ 6.56E5
~ 3.28E5
µCi/sec
µCi/sec
~ 2.36E5
~ l.18E5 cpm
- cpm
~ I.35E5
~ 6.75E4 cps
µCi/sec
µCi/sec
µCi/sec
- IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized.
<1>Each Mirion PING Monitor skid is equipped with a low range monitor (LRNG) and a high range monitor (HRNG). The low range monitor has three setpoints: ALERT, HIGH, and HIGH-HIGH. The HIGH-HIGH setooint will be used to swap from the low range monitor to the high range monitor.
The setpoints were determined using a calculated mix from the UFSAR and discharge flow rate of 1450 cfin for PV-1/2.
The calculational method below was used to derive the monitor setpoints for the following operational conditions:
Continuous release via PV-1/2.
Batch release ofBV-1 or BV-2 Waste Gas Decay Tank via PV-1/2.
Batch release ofBV-1 or BV-2 Containment Purge via PV-1/2 is not shown in the above table. However, if it is necessary to perform a BV-1 1or BV-2 Containment Purge via this release point, the alarm setpoint shall be calculated in accordance with Section 8.1.3.2.
Procedure Number:
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30 of 131 ODCM: GASEOUS EFFLUENTS 8.1.3.1.1 8.1.3.1.2 BV-1/2 Mix Radionuclides The "mix (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
The gaseous source terms that are representative of the "mix" of the gaseous effluent were evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. The gaseous source terms can be obtained from ATTACHMENT A Tables 2.1-la. and 2.1-lb.
The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was calculated by:
[2.1-9]
where:
Ai
= The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la and 2.1.lb.
BV-1/2 Maximum Acceptable Release Rate {Whole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was determined by:
[2.1.10]
where:
V; = The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrem/year/uCi/sec) from ATTACHMENT G Table 2.2-12.
S; = From equation [2.1-9]
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31 of 111 8.1.3.1.3 8.1.3.1.4 8.1.3.1.5 11 BV-1/2 Maximum Acceptable Release Rate (Skin Exposure)
Qt was also determined based upon the skin exposure limit as follows:
3000 Qt=~~~~~~-
L [Li(X/Q)pv + 1.1Bi]Si i
[2.1-11]
where:
Li
= The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
(X/Q)pv = The highest calculated annual average relative concentration of effluents releases via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-6.
(X/q)pv
= 2.31E-6 sec/m3 (0.5 - l.O miles)
= The highest calculated short term relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT N Table 2.3-38.
= l.07E-5 sec/m3 (0.5 - 1.0 miles)
Bi
= The constant for long term releases (greater than 500 hrs/year) for noble gas radionuclide "i accounting for the gamma radiation dose from the elevated finite plume (mrad/year/uCi/sec) from ATTACHMENT G Table 2.2-12.
BV-1/2 Maximum Acceptable Release Rate andividual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by:
[2.1-12]
NOTE: Use the lower of the Qi values obtained in Section 8.1.3.1.2 and 8.1.3.1.3.
BV-1/2 Maximum Acceptable Concentrations andividual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide in the gaseous effluent was determined by:
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32 of 131 8.1.3.1.6 8.1.3.1.7 Ci = 2.12E-3 Qi F
where:
[2.1-13]
2.12E-3 = Unit conversion factor (60 sec/minx 3.53E-5 ft3/cc).
F
= The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.3.1.
BV-1/2 Monitor Count Rate The calculated monitor count rate (ncpm for Victoreen Monitors and ncps for Mirian Monitors) above background attributed to the noble gas radionuclide.
(CR) was determined by:
[2.1-14]
where:
Ei
= The detection efficiency of the monitor for noble gas radionuclide 11i 11
( cpm/uCi/cc for Victoreen or cps/uCi/cc for Mirion) from ATTACHMENT B Table 2.1-2a and 2.1-2b.
BV-1/2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:
The Victoreen monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by:
HHSP = 0.60 x CR
[2.1-15]
The Victoreen monitor HIGH Alarm Setpoint above background (ncpm) was determined by:
HSP = 0.30 x CR
[2.1-16]
The Mirian monitor HIGH Alarm Setpoint above background (uCi/sec) was determined by:
HSP = 0.60 x Qt
[2.1-17]
The Mirian monitor ALERT Alarm Setpoint above background (uCi/sec) was determined by:
ASP = 0.30 x Qt
[2.1-18]
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8.1.3.2 8.1.3.2.1 11 3~ ofnl NOTE: Use the lower of the Qt values obtained in Section 8.1.3.1.2 and 8.1.3.1.3.
BV-1/2 Setpoint Determination Based On Analysis Prior To Release For PV-1/2 Elevated Releases The following calculation method applies to gaseous releases via the PV-1/2 Gaseous Waste/Process Vent'when the "calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the BV-1/2 Gaseous Waste Gas Monitor (RM-GW-l 08B) or alternate (RM-IGW-109 LRNG) during the following operational conditions:
Continuous release via PV -1/2.
Batch release ofBV-1 or BV-2 Waste Gas Decay Tank via PV-1/2.
Batch release ?fBV.:*l or BV-2 Containment Purge via PV-1/2.
\\
BV-1/2 Maximum Acceptable Release Rate Determine the maximum acceptable discharge flow rate for the release from the Process Vent for the analyzed mix.
The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by:
[2.1-21].
where:
1.06
= 500 mrem/yr x 2.12E-3
- 500 mrem/yr
= dose rate limit, whole body exposure 2.12E-3
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
S
= Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.3.
Vi
= The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume (mrem/year/uCi/sec) from ATTACHMENT G Table 2.2-12.
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34 of 131 Ci
= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
Based upon the skin exposure limit, (f) is calculated by:
6.36 S f=--------
4 [Li (X/Q)pv + 1.1Bi] Ci
[2.1-22]
t where:
6.36
=
3000 mrem/yr x 2.12E-3 3000 mrem/yr 2.12E-3
= dose rate limit, skin exposure
= unit conversion factor
= (60 sec/minx 3.53E-5 ft3/cc)
The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.
(X/Q)pv =
The highest calculated annual average relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENT F Table 2.2-6.
(X/q)pv
=
2.3 lE-(i sec/m3
=
The highest calculated short term relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3) from ATTACHMENTN Table 2.3-38.
=
l.07E-5 sec/m3
=
The constant for long-term releases (greater than 500 hrs/year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/year/uCi/sec) from ATTACHMENT G Table 2.2-12.
Select the smaller of the calculated fvalues based on the whole body exposure limit and based on the skin exposure limit shown above. The actual discharge flow rate
( cfin) must be maintained at or below this (f) value.
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82 8.1.3.2.2 where:
11 1" of 111 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
The calculated monitor HIGH-HIGH Alarm Setpoint above background (n.cpm) attributed to the noble gas radionuclides is determined by:
HHSP=
p'
[2.1-23]
f
= The maximum acceptable gaseous discharge flow rate (cfin) determined in Section 8.1.3.2.1.
F'
= The maximum actual or design effluent flow rate (cfin) at the point.
of release.
= 1450 cfin for PV-1/2 Ci
= The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
Ei
= The detection efficiency of the respective monitor (RM-1GW-108B) or (RM-I GW-109 LRNG) for noble gas radionuclide "i"
( cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.l-2b.
When a HIGH-HIGH Alarm Setpointhas been calculated according to this section the monitor HIGH Alarm setpoint above background (ncpm) is determined by:
HSP = HHSP x 0.5
[2.1-24]
Compliance With 10 CFR 20 Dose Rate Limits (ODCM CONTROL 3.11.2.1) 8.2.1 Dose Rate Due To Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents from the site is limited to 500 mrem/yr to the total body and 3,000 mrem/yr to the skin. Site gaseous
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%of Bl effluents are the total ofBV-1 and BV-2 specific ground releases and a shared elevated release, the PV-1/2 Gaseous Waste/Process Vent. Based upon NUREG-0133 <3.13.1) the following equations are used to show compliance with ODCM CONTROL 3.11.2.1.a.
L [ViQis + Ki(X/Q)v Qiv] < 500 mrem/yr i
[2.2-1]
L ((Li(X/Q)s + 1.1Bd Qis + [Li + 1.1Mi] (X/Q)v Qiv] ~ 3000 mrem/y_r [2.2-2]
i where:
=
=
=
1.1 The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i'", mrem/year/uCi/m3*
The skin dose factor due to beta emissions for each identified noble gas radionuclide "i", mrern/year/uCi/m3*
The air dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrad/year/uCi/m3.
The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrem/year/uCi/sec.
The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad/year/uCi/sec.
The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrern/mrad.
The release rate of noble gas radionuclide "i" in gaseous effluents from free-standing stack, uCi/sec.
The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCi/sec.
(XI Q )s = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/m3).
(XI Q)v = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for ground releases (sec/m3).
At the Beaver Valley site gaseous releases may occur from the following Release Points (RPs) as shown in ATTACHMENTP Figure 2.4.2:
RP 1 & 4. The BV-1 Auxiliary Building Vent and the BV-2 SLCRS Unfiltered Pathway atop the Auxiliary Buildings (VV-1 and VV-2)
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11 37 of 131 RP 2 & 5. The BV-1 Rx Containment/SLCRS Vent and the BV-2 SLCRS Filtered Pathway atop the Containment Domes (CV-1 and CV-2)
RP 3.
The BV-1/2 Gaseous Waste/Process Vent atop the BV-1 Cooling Tower (PV-1/2)
RP 6.
The BV-2 Condensate Polishing Building Vent (CB-2)
RP 7.
Th~ BV-2 Waste Gas Storage Vault Vent (WV-2)
RP 8.
The BV-2 Decontamination Building Vent (DV-2)
RP 9.
The BV-2 Turbine Building Vent (TV-2}
The effluents from Release Point 1 & 4 are ground level.in nature. At BV-1 the sources of these releases are Containment Purges and normal Auxiliary Building Ventilation. At BV-2 the sources of these releases are Containment Purges and Contiguous Area ventilation.
Effluent from the Release Point 2 & 5 are assumed ground level in nature. At BV-1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS). At BV-2 the source of these releases is normal Auxiliary Building Ventilation. It is also possible to release Containment Purges from these vents.
Release Points 6, 7, 8 and 9 are not normally radioactive release points.
The effluent from Release Point 3 are elevated, and the sources of these releases are the Main Condenser Air Ejectors, the Waste Gas Decay Tanks and the Containment Vacuum Pumps.
Noble gas releases may normally occur from Release Points 1 through 5 above. To show compliance with the site limits of ODCM CONTROL 3.1 l.2.1.a, Equations [2.2-1] and
[2.2-2] are expressed in terms of the actual release points for the site. Note that the expressions for release points 6, 7, 8 and 9 are included for use if radioactive releases via these release points are identified in the future.
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. ODCM: GASEOUS EFFLUENTS iR of Bl 8.2.1.1 Total Body Dose Rate (All Release Points)
~ ViQipv + LKi [(X/Q)cv Qicv1 + (X/Q)vv Qivvi + (X/Q)cv Qicv2 + (X/Q)vv l
- 500 mrem/yr
[2.2-3]
8.2.1.2 Skin Dose Rate {All Release Points)
(X/Q)vv. Qivv1 +
(X/Q)cv Qicv2 + (X/Q)vv Qivv2 + (X/Q)tv Qitv2 +
(X/Q)cb Qicb2 + (X/Q)dv where:
Q.
1 pv Q.
1 cv2 Q.
1 vvl Q.
1 vv2 Q.
1 tv2 Q.
1 cb Q.
1 dv2 Q.
1 wv2
[2.2-4]
= Release rate of radionuclide "i" from the PV-1/2, uCi/sec.
= Release rate of radionuclide "i" from CV-I, uCi/sec.
= Release rate ofradionuclide "i" from CV-2, uCi/sec.
= Release rate of radionuclide "i" fromVV-1 Auxiliary Building, uCi/sec.
= Release rate of radionuclide "i" from VV-2, uCi/sec.
= Release rate ofradionuclide "i" from TV-2, uCi/sec.
= Release rate ofradionuclide "i" from CB-2, uCi/sec.
= Release rate ofradionuclide "i" from DV-2, uCi/sec.
= Release rate ofradionuclide "i" from WV-2, uCi/sec.
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'N of 131 11 (X / Q )pv
= Highest calculated annual average relative concentration for releases from the PV-1/2, sec/m3*
1 (X / Q )cv
= Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m3*
(X/Q)vv
= Highest calculated annual average relative concentration for releases from VV-1 and VV-2, sec/m3.
(X / Q )tv Highest calculated annual average relative concentration for releases for TV-2, sec/m3*
(X/Q)cb
= Highest calculated annual average relative concentration for releases for CB-2, sec/m3*
(X/Q)dv
= Highest calculated annual average relative concentration for releases for DV-2, sec/m3.
(X / Q )wv
= Highest calculated annual average relative concentration for releases for WV-2, sec/m3*
I The release rate for a containment purge is based on an averaged release rate in uCi/sec for the entire purge (not to exceed 960 min in accordance with ODCM CONTROL 3.11.2.1).
All other terms remain the same as those defined previously.
For the site, 4 potential modes ofrelease are possible. The release modes identify the various combinations of sources of radioactivity and their release points which are used to determine the controlling locations. They are presented in ATTACHMENT C Table 2.2-1.
For* Release Modes I, 2, and 3, the controlling location for implementation of ODCM CONTROL 3.11.2.1.a is 0.35 miles NW. Inserting the appropriate X/Q's from ATTACHMENT F Tables 2.2-4 through 2.2-10 for this location, Equations [2.2-3] and
[2.2-4] become:
8.2.1.3 Total Body Dose Rate (at 0.35 Miles NW)
LViQi
+ "f.Ki [9.24E - 5 ~ Qi 1 + 1.03E - 4 Qi 1 + 9.24E - 5 Qi 2 +
i pv i
CV VV CV 1.03E - 4 Qi 2 + 7.35E - 5 Qi 2 + 9.24E - 5 Qi 2 + 9.24E - 5 Q1 2 +
vv tv dv wv 7.35E - 5 Qi 2 ] *
- s;;
SOOmrem/yr cb
[2.2-5]
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40 of Bl 11 8.2.1.4 Skin Dose Rate (at 0.35 Miles NW)
L [7.0E -10 ~ Li + 1.1Bil Qi L [Li + 1.1Mil + 9.24£ - 5 Qi 1 + 1.03£ i
pv i CV
-4
+ 9.24£ - 5 Qi 2 + 1.03£ - 4 Qi 2 + 7.35£ - 5 Qi 2 + 9.24£ - 5 Qi 2
CV VV W
~
+
9.24£ - 5 Qi 2 + 7.35£ - 5 Qi 21 :S 3000 mrem/yr
. WV Cb
[2.2-61 For Release Mode 4, the controlling location is 0.75 miles N. Inserting the appropriate X/Qs from ATTACHMENT F Tables 2.2-4 through 2.2-10 for this location, Equations
[2.2-3 and 2.2-41 become:
8.2.1.5 Total Body Dose Rate (at 0.75 Miles N) 4 Vi Qipv + L Ki [3.95£ - 6 Qi 1 + 4.99£ - 6 Qi 1 + 3.95£ - 6 Qi 2 + 4.99£ l
i CV VV CV 6 Qi 2 + 4.26£ - 6 Qi 2. + 3.95£ - 6 Qi 2 + 3.95£ - 6 Qi 2 + 4.26£ - 6 Qi 21 vv tv dv wv cb
- S 500 ~ mrem/yr
[2.2-7]
8.2.1.6 Skin Dose Rate {at 0.75 Miles N)
L [2.31£ - 6 Li + 1.1Bd Qi + L [Li + 1.1Md [3.95£ - 6 Qi 1 + 4.99£ - 6 Qi 1 +
i pv i
CV VV 3.95£ - 6 Qi 2 + 4.99£ - 6 Qi 2 + 4.26£ - 6 Qi 2 + 3.95£ - 6 Qidv + 3.95£ - 6 CV VV ro Qiwv + 4.26£ - 6 Qicb] ~ :S 3000 mrem/yr
[2.2-81 8.2.1.7 Determination of Controlling Location The determination of controlling location for implementation of ODCM CONTROL 3.11.2.1.a for noble gases is a function of the following parameters:
I.
Radionuclide mix and their isotopic release rate Release Mode Meteorology The incorporation of these 3 parameters into Equations [2.2-3] and [2.2-4] resulted in the equations for the controlling locations as presented in Equations [2.2-5 through 2.2-8].
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11 41 of 111 The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GASlBB (similar to NUREG-0017.<3.u.4) Inputs were based on operating modes of the respective plants. The code inputs utilized are presented in 1/2-0DC-3.0h The source term is presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.
The X/Q values utilized in the equations for implementation of ODCM.
CONTROL 3.11.2.1.a are based upon the maximum long-term annual average X/Q in the unrestricted area. ATTACHMENT E Table 2.2-3 presents the distances from the Release Points to the nearest unrestricted area for each of the 16 sectors as well as to the nearest vegetable garden, cow, goat, and beef animal. ATTACHMENT F Tables 2.2-4 through 2.2-10 present the long-term annual average (X/Q) values for all Release Points to the special locations presented in ATTACHMENT E Table 2.2-3. A description of their derivation is provided in I/2-0DC-3.01.
For Release Modes 1, 2, and 3, dose calcu~ations were performed using the highest calculated site boundary X/Q values applicable to the release points involved and the projected radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release could contribute to the dose at a given location, the selection of the two highest sector X/Q values at the site boundary considered this contribution. From these results, the distance and sector associated with the highest calculated site boundary dose were selected as the controlling location.
For Release Modes 1, 2, and 3 the controlling location is 0.35 miles NW. In Release Mode 1, the dominant release is via VV-1 and CV-2. In Release Modes 2 and 3, the
/-dominant release is a Containment Purge from the VV-1 or VV-2.
For Release Mode 4, a similar evaluation was performed. Long-term annual average X/Q values were calculated at the mid-point of the 10 standard distances listed in ATTACHMENT F Table 2.2-4 through 2.2-10. In that a simultaneous, ground level release could contribute to the dose at a given locatio°", the selection of the two highest X/Q values at the controlling distance considered this contribution. Since the two maximum X/Q values occurred in the 0.5 - 1.0 mile radial band, the controlling distance was selected at 0.75 miles. From the calculated dose results, the controlling sector was shown to be North. In this Release Mqde, the dominant release is a Containment Purge via the PV-1/2 Gaseous Waste/Process Vent. Neither of the controlling receptor locations are presently inhabited.
Values for Ki, Li, and Mi, which were used in the determination of the controlling receptor location and which are to be used in Equations [2.2-5] through [2.2-8] to show compliance with ODCM CONTROL 3.11.2.1.2, are presented in Table 2.2-11.
Values taken from Table B-1 ofNRC Regulatory Guide 1.109, Revision 1, <3.u.s) were multiplied by 1E6 to convert picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.
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42 of 1 i]
Values for Vi and Bi for the finite plume model can be expressed as shown in Equation [2.2-9] and [2.2-1 O]. Values were calculated using the NRC code RABFIN at the site boundary location which would receive the highest total dose from all Release Points. These values are presented in ATTACHMENT G Table 2.2-12 and calculated from the following equation:
[2.2-9]
where:
I
= The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (uj) and atmospheric stability class "k" for a particular wind direction.
K = A numerical constant representing unit conversions.
=
(260 mrad)(radians) (m3 ) (transformation) [ 16 sectors ]
(sec)(Mev)(Ci) 2n radians
[1E-6 ~:i] [3.15£7 ;;]
= 2.1E4 mrad (m3) (transformation)/yr(Mev)(uCi).
rd
= The distance from the release point to the receptor location, meters.
Uj
= The mean wind speed assigned to the "j" th wind speed class, meters/sec.
fjk = The joint frequency of occurrence of the j" th wind speed class and kth stability class (dimensionless).
A1i = The number of photons.of energy corresponding to the "l" th energy group emitted per transformation of the "i" th radionuclide, number/transformation.
E1 = The energy assigned to the "l" th energy group, Mev.
Ua = The energy absorption coefficient in air for photon energy H1, meters *1*
The Vi factor is computed with conversion from air dose to tissue depth dose, thus:
[2.2-10]
where:
UT = The tissue energy absorption coefficient for photons of energy E1, cm2/gm.
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11 43 of Bl T d = The tissue density thickness taken to represent the total body dose (5gm/cm2).
1.1 = The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad.
8.2.2
- Dose Rate Due To Radioiodines And Particulates The dose rate in unrestricted areas resulting from the of inhalation ofl-131, tritium, and all radionuclides in particulate form ( excluding C-14) with half lives greater than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem/yr to any organ.
Based upon NUREG-0133,<3.u.1) the following basic equation is used to show compliance with ODCM CONTROL 3.11.2.l.b:
L Pi1: [(X/Q) 5 Qis + (X/Q)v Qiv]
1,500 mrem/yr i
where:
[2.2-11]
Pi't
= Dose parameter for any organ -r for each identified radionuclide "i",
mrem/yr per uCi/m3.
Qis
= The release rate ofradionuclide "i", in gaseous effluents from elevated releases, uCi/sec.
Qiv
= The release rate ofradionuclide "i", in gaseous effluents from ground level releases, uCi/sec.
(X/Q) s = The highest calculated annual average relative concentration at the unrestricted area boundary for elevated releases, sec/m 3*
(X/QJv = The highest calculated annual average relative concentration at the unrestricted area boundary for ground level releases, sec/m 3*
NOTE:
The dispersion parameters specifi_ed in Section 8.2.2 are limited to the site boundary as defined above.
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A.A. of 131 Releases may occur from any Release Point in the Release Modes listed in ATTACHMENT C Table 2.2-1. To show compliance with ODCM CONTROL 3.11.2.1.b, Equation [2.2-11] is now expressed in terms of the actual Release Points for the site.
[2.2-12]
where:
(X/Q)pv = Highest calculated annual average relative concentration for releases from PV-1/2, sec/m3.
(X/Q) cv = Highest calculated annual average relative concentration for releases from CV-I and CV-2, sec/m3.
(X/Q)vv = Highest calculated annual average relative concentration for releases from VV.;1 and VV-2, sec/m3*
(X/Qtv = Highest calculated annual average relative concentration for releases from TV-2, sec/m3.
(X/Q) ch = Highest calculated annual average relative concentration for releases
- from CB-2, sec/m3*
(X/Q) dv = Highest calculated annual average relative concentration for releases from DV-2, sec/m3.
(X/Q)wv = Highest calculated annual average relative concentration for release from
~
WV-2, sec/m3.
Q.
= Long-term release rate of radionuclide "i" from PV-1/2, uCi/sec.
1 pv Q.
= Long-term release rate of radionuclide "i" from CV-I, uCi/sec.
1cvl
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4"i oflil 11 Qi
=,Long-term release rate ofradionuclide "i" from CV-2, uCi/sec.
cv2 Qi
= Long-term release rate of radionuclide "i" from VV-1, uCi/sec.
vvl Q.
= Long-term release rate of radionuclide "i" from VV-2, uCi/sec.
1vv2 Q.
= Long-term release rate of radionuclide "i" fromTV-2, uCi/sec.
1tv2 Q.
=
1cb2 Long-term release rate ofradionuclide "i" from CB-2, uCi/sec.
Q.
=
1dv2 Long-term release rate of radionuclide "i" from DV-2, uCi/sec.
Q.
=
1 wv2 Long-term release rate of radionuclide "i" from WV-2, uCi/sec.
All other terms are the same as those defined previously.
r TV-2, CB-2, DV-2 and WV-2 are not normal radioactive Release Points.. These Release Points are included only for use if radioactive releases via these vents are identified in the future. In the calculation to show compliance with ODCM CONTROL 3.11.2.1.b only the inhalation pathway is considered.
Values of the organ dose parameters, PiT, were calculated using methodology given in NUREG-0133.<3.u.1) For the child age group, the following equation was used for all nuclides. The PiT, values are presented in ATTACHMENT H Table 2.2-13.
[2.2-13]
where:
3.7E9 =
Breathing rate of child (3,700 m3/yr) x unit conversion factor (1E6 pCi/uCi).
DF AiT =
The organ inhalation dose factor for a child from Table 6 of NUREG-OJ 72 (3.u.6) or ERS-LMR-15-006 <3.u.z&) (Se-75) for organ T, nuclide "i", in units of mrem/pCi.
For Release Modes 1 through 4, the controlling location is the site boundary, 0.35 miles NW.
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46of111 ODCM: GASEOUS EFFLUENTS 8.3 Equation [2.2-12] becomes:
8.2.2.1
~ PiT [7.00E - 10 Qipv + 9.24£ - 5 Qicv + 1.03£ - 4 Qivvi + 7.35£ - 5 Qitvi +
9.24£ - 5 Qicvz + 1.03£ - 4 Qivvz + 7.35£ - 5 Qitv2 + 7.35£ - 5 Qicbz + 9.24£ - 5
[2.2-14]
Determination of Controlling Location The determination of the controlling location for implementation of ODCM CONTROL 3.11.2.1.b for radioiodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Equation [2.2-12] results in the respective equations for each Release Mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.
In the determination of the controlling site boundary for each Release Mode, the highest 2 site boundary X/Q values for each Release Point were utilized in conjunction with the radionuclide mix and the release rate for each Release Point to determine the controlling location.
The Pi~ values are presented in ATTACHMENT H Table 2.2-13.
The X/Q values in Equation [2.2-14] were obtained from ATTACHMENT F Tables 2.2-4 through 2.2-10.
A description of the derivation of the X/Q values is provided in l/2-0DC-3.01.
Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)
{Gaseous)
At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radwaste system., The effluent from both units are mixed and discharged from a common Release Point, the PV-1/2 Gaseous Waste/Process Vent, at the top of the Unit 1 Cooling Tower. The resulting dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception would be a Containment Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5.
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11 47ofl31 8.3.1 Dose Due To Noble Gases 8.3.1.1 8.3.1.1.1 Cumulation Of DosesSection II.B.1 of Appendix I of 10 CFR 50 (ODCM CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. In addition, ODCM CONTROL 3.11.2.4 requires use ofradwaste system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta. Based upon NUREG-0133,<3.1.3.I) the air dose limits in the unrestricted area due to noble gases released in gaseous effluents are defined by the following equations:
Gamma Radiation Quarter Limit 3.17E - 8 t [Mi [(X/Q)vQiv + (X/q)vqiv] + [BiQis + biqisJ]
- 5 mrad [2.3-1]
l 8.3.1.1.2 Beta Radiation Quarter Limit 3.17E-8 4 Ni [(X/Q)vQiv + (X/q)yqiv + (X/Q) 5 Qis + (X/q) 5 qis]
10 mrad l
[2.3-2]
8.3.1.1.3 Gamma Radiation Year Limit
[2.3-3]
8.3.1.1.4 Beta Radiation Year Limit 3.17E - 8 4 Ni [(X/Q)vQiv + (X/q)vqiv + (X/Q) 5 Qis + (X/q) 5 qis]
20 mrad l
[2.3-4]
8.3.1.1.5 Gamma Radiation Proiection Averaged Over 31 Days 3.17E ~ 8 t [Mi [(X/Q)vQiv + (X/q)vqiv] + [BiQis + biqisJ]
0.2 mrad[2.3-5]
l
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4R of 111 8.3.1.1.6 Beta Radiation Projection Averaged Over 31 Days 3.17£ - 8 ~ Ni [(X/Q)vQiv + (X/q)vqiv + (X/Q) 5 Qis + (X/q) 5qis] ~ 0.4 mrad l
[2.3-6]
where:
Mi
= The air dose factor due to gamma emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m3).
Ni
= The air dose factor due to beta emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m3).
(X./QJv =. The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases greater than 500 hrs/year (sec/m3).
(X/q)v
= The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases equal to or less than 500 hrs/year (sec/m3).
(X/Q) 5 = The annual average relative concentration for areas.at or beyond the unrestricted area boundary for long-term free standing stack releases greater than 500 hrs/year (sec/m3).
(X/q)s = The relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases equal to or less than 500 hrs/year (sec/m3).
qis
= Release of noble gas radionuclide "i" in gaseous effluents for short-term stack releases equal to or less than 500 hrs/year (uCi).
qiv
= Release of noble gas radionuclide "i" in gaseous effluents for short-term vent releases equal to or less than 500 hrs/year (uCi).
Qis
= Release of noble gas radionuclide "i" in gaseous effluents for long-term free standing stack releases greater than 500 hrs/year (uCi).
Qiv
= Release of noble gas radionuclide "i" in gaseous effluents for long-term vent releases greater than 500 hrs/year (uCi).
Bi
= The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec ).
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11 4(} of 131 bi
= The constant for short-term releases (equal to or less than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).
3.17E-8 = The inverse of the number of seconds in a year.
NUREG 0133(3.1 3.1) permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions. This special consideration is applied in Equations [2.3-1] through
[2.3-6], however, a summary of the "real time" meteorological data coupled with the corresponding releases shall be included in the Annual Radioactive Effluent Release Report.
Short-term releases are also evaluated annually in computer codes technically consistent with XOQDOQ and GASPAR for inclusion in the Annual Radiological Environmental Report.
The incorporation of this option and the Release Modes of ATTACHMENT I Table 2.3-1 results in the following equations to show compliance with 10 CFR 50 for the calendar quarter or year.
8.3.1.1.7 Gamma Radiation Dose Equation 3.17E-8_L i
[Mi [(X/Q)cvQicv + (X/Q)vvQivv + (X/Q)cbQicb + (X/Q)dvQidv +
- s._0.2 mrad (per 31 days), or
,:S 5.0 mrad (per quarter), or
.:::_10.0 mrad (per year)
[2.3-7]
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11 "Ooflil 8.3.1.1.8 Beta Radiation Dose Equation 3.17£ - 8 4 Ni [(X/Q)cvQicv + (X/Q)vvQivv + (X/Q)cbQicb + (X/Q)dvQidv +
l
.::: 0.4 mrad (per 31 days), or
,::: 10.0 mrad (per quarter), or
.::: 20.0 mrad (per year) where:
[2.3-8]
(X/Q) cv = Annual average relative concentration for releases from CV-1 and CV-2 (sec/m3).
(X/Q)w = Annual average relative concentration for releases from VV-1 and VV-2 (sec/m3).
(X/Q\\v = Annual average relative concentration for releases from PV-1/2 (sec/m3).
(X/Q)tv = Annual average relative concentration for releases from TV-2 (sec/m3).
Q.
= Release ofradionuclide "i" from CV-1 and CV-2 (uCi).
1 CV Q.
= Release or radionuclide "i" from VV-1 and VV-2 (uCi).
1 vv Q.
= Release ofradionuclide "i" from PV-1/2 (uCi).
1 pv Q.
= Release of radionuclide "i" from TV-2 (uCi).
1 tv Q.
= Release ofradionuclide "i" from the CB-2 (uCi).
1 cb Q.
Release of radionuclide "i" from DV-2 (uCi).
1 dv Q.
= Release of radionuclide "i" from WV-2 (uCi).
1 WV
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"1 of 111 For Release Modes 1, 2, 3, and 4 the controlling location is 0.35 miles NW. Substitution of the appropriate X/Q values into Equations [2.3-7] and [2.3-8] results in the following:
8.3.1.1.9 Gamma Radiation Dose Determination 3.17£ - 8 ~ [Mi[9.24E - 5 Qicv + 1.03E - 4 Qivv + 7.35E - 5 Qitv + 7.35E - 5 Qicb +
i
[2.3-9]
- S 0.2 mrad (per 31 days), or
- S 5.0 mrad (per quarter), or
- S 10.0 mrad (per year) 8.3.1.1.10 Beta Radiation Dose Determination 3.17E - 8 L Ni[9.24E - 5 Qi
+ 1.03E - 4 Qi
+ 7.35E-5 Qitv + 7.35E-5 Qicb +
i CV VV 9.24£ - 5 Qidv + 9.24£ - 5 Qiwv + (0.5) 7.0E - 10 Qipv]
- S 0.4 mrad (per 31 days), or
[2.3-10]
- S 10.0 mrad (per quarter), or
- S20.0 mrad (per year) 8.3.1.1.11 Determination of Controlling Location The determination of the controlling locations for implementation of IO CFR 50 is a function of the following parameters:
Radionuclide mix and their isotopic release I
Release Mode Meteorology The incorporation of these parameters into Equations [2.3-7] and [2.3-8]
resulted in the equations for the controlling locations as presented in Equations
[2.3-9] and [2.3-10]. the radionuclide mix was based upon source terms calculated using the NRC GALE Code (see l/2-0DC-3.01 for inputs) and are shown in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function ofrelease type and Release Point.
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~2 of LH As in Section 8.2.1, for each Release Mode, the two highest boundary X/Q values for each release point and, release duration were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since elevated releases occur from the BVPS site and their maximum X/Q values may not decrease with distance (i.e.,
the site boundary may not have highest X/Q values), the two highest X/Q values for those distances, greater than the site boundary, were also considered in conjunction with the radionuclide mix to determine the controlling location.
These values ofX/Q were obtained for the midpoint of the 10 standard distance intervals previously presented in ATTACHMENT F Tables 2.2-4 through 2.2-10.
For each Release Mode, a particular combination of Release Point mix and meteorology dominates inthe determination of the controlling location. For Release Modes 1, 2, 3, and 4 the controlling release is VV-1 and VV-2. For Release Mode 3, the controlling release is CV-1 and CV-2.
Values for Mi and Ni, which were used in the determination of the controlling location and which are to be used by BV-1 ai;id BV-2 in Equations [2.3-9] and
[2.3-10] to show compliance with 10 CFR 50 were presented in ATTACHMENT G Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, Revision 1 (3.1.3.S) were multiplied by 1E6 to convert from picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.
In determination of the controlling location for Release Modes 1, 2, 3, and 4, ATTACHMENT F Tables 2.2-4 through 2.2-7 are utilized for X/Q values.
The Bi values to be utilized are the same values which were presented in ATTACHMENT G Table 2.2-12. A description of the derivation of the various X/Q values is presented in l/2-0DC-3.01.
The following relationship must hold for BV-1 or BV-2 to show compliance with ODCM CONTROL 3.11.2.2:
For The Calendar Quarter Dr:::: 5.0 mrad D13:::: 10 mrad For Th~ Calendar Year Dr:::: 10 mrad D13::::20mrad where:
Dr = The air dose from gamma radiation (mrad).
D13 = The air dose from beta radiation (mrad).
[2.3-11]
[2.3-12]
[2.3-13]
[2.3-14]
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8.3.1.2 8.3.1.2.1 11 5~ of Bl The quarterly limits given above represent one-half the annual design objective of Section II.BJ of Appendix I of 10 CFR 50. If any of the limits of Equations
[2.3-11] through [2.3-14]' are exceeded, a special report pursuant to both.
Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations.
In addition, ODCM CONTROL 3.1.2.4 requires that the gaseous radwaste system must be used to reduce radioactive materials in that waste when projected doses from each reactor unit when averaged over 31 days exceed any of the following:
Dr_::: 0.2 mrad D13 _::: 0.4 mrad Proiection Of Doses (Noble Gas}
[2.3-15]
[2.3-16]
Doses due to gaseous releases from BV-1 and BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.2.2 Projection Of Doses for additional specifications). The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. (Also see Section 8.3.2.2 Projection Of Doses for additional specifications). The doses used in the 31-day dose projection will be calculated using Equations [2.3-9] and [2.3-1 O] as appropriate. The 31-day dose projection shall be performed according to the following equations:
When Including Pre-Release Data,
[A+ B]
D31 -
-T-(31) + C
[2.3-17]
8.3.. 1.2.2
- When Not Including Pre-Release Data,
[2.3-18]
\\\\'here:
D31
= Projected 31 day dose (mrad).
A
= Cumulative dose for quarter (mrad).
B
= Projected dose from this release (mrad).
T
= Current days into quarter.
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~4 of 111 C
= Value which may be used to anticipate plant trends (mrad).
8.3.2 Dose Due To Radioiodines And Particulates 8.3.2.1 8.3.2.1.1
(
Cum1rlation Of DosesSection II.C of Appendix I ofl O CFR 50 (ODCM CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radioiodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose commitment to an individual in,an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition, ODCM CONTROL 3.11.2.4 requires the use of gaseous radwaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon NUREG-0133,(3* 13J) the dose to an organ of an individual from radioiodines and particulates, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following equation:
Radioiodines and Particulates Month, Quarter, and Year Limits
- 0.3 mrem (per 31 days), or
- 7. 5 mrem (per quarter), or
- 15.0 mrem (per calendar year) where
[2.3-19]
Qis
= Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs/yr (~Ci).
Qiv
= Release of radionuclide "i" for long-term vent releases greater than 500 hrs/yr (uCi).
qis
= Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs/yr (uCi).
qiv
= Release ofradionuclide "i" for short-term vent releases equal to or less than 500 hrs/yr (uCi).
W s
= Dispersion parameter for estimating dose to an individual at the controlling location for long-term free-standing stack releases greater than 500 hrs/yr.
= sec/m3 for the inhalation pathway, (X / Q)s.
= meters-2 for the food and ground plane pathway, (D /Q)s.
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8.3.2.1.2 Wv 11
.c;.c; of 131
= The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs/yr.
= sec/m3 for the inhalation pathway, (X / Q)v.
= meters*2 for the food and ground plane pathway, (D /Q)v.
Ws
= Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases equal to or less than 500 hrs/yr.
= sec/m3 for the inhalation pathway, (X / q )s.
= meters*2 for the food and ground plane pathway, ( D / q )s.
Wv
= The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases equal to or less than 500 hrs/yr.
= sec/m3 for the inhalation pathway, (X/ q)v.
= meters*2 for the food and ground plane pathway, (D / q)v.
- 3. l 7E-8 = The inverse of the number of seconds in a year.
Ri,
= The dose factor for each identified radionuclide "i" for the organ "'t" of interest (mrem/yr per uCi/sec per m*2 or mrem/yr per uCi/m3).
Radionuclides and particulates may be released from any of the BV-1 and BV-2 Release Points in the Release Modes identified in ATTACHMENT I Table 2.3-1. As described previously in Section 8.3.1.1, NUREG 0133(3.u.1) permits use of long-term annual average dispersion calculations (which with the release modes of Table 2.3-1 results in the following equations) to show compliance with ODCM CONTROLS 3.11.2.3 and 3.11.2.4. For a particular organ, Equation [2.3-19] becomes:
Radioiodines and Particulates Dose Equation
- 0.3 mrem (per 31 days), or
- 7.5 mrem (per quarter), or
- 15.0 mrem (per calendar year)
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S6 of Bl where:
0.5 Wpv Wcv Wvv Web Wwv Q.
l pv
= Dispersion parameter for releases from PV-1/2. The value of 0.5 represents the portion of dose assigned to each Unit due to this being a shared Release Point
= Dispersion parameter for releases from CV-I and CV-2.
= Dispersion parameter for releases from VV-1 and VV-2.
= Dispersion parameter for releases from TV-2.
= Dispersion parameter for releases from CB-2.
= Dispersion parameter for releases from DV-2.
= Dispersion parameter for releases from WV-2.
= Release ofradionuclide "i" from PV-1/2 (uCi).
Qi
= Release of radionuclide "i" from CV-1 and CV-2 (uCi).
CV Qi
= Release ofradionuclide "i" from VV-1 and VV-2 (uCi).
vv Qi
= Release of radionuclide "i" from TV-2 (uCi).
tv Qi
= Release ofradionuclide "i" from CB-2 (uCi).
cb Qi
= Release of radionuclide "i" from DV-2{uCi).
dv Qi
= Release ofradionuclide "i" from WV-2 (uCi).
WV TV-2, CB-2, DV-2 and WV-2 are not normally radioactive Release Points.
These are included only for use if a radioactive release is identified in the future.
In determining the dose at a particular location, dispersion parameter W is a function of the pathway. For the food and ground plane pathway, Wis in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q.
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8.3.2.1.2.1 0
11 t::,7 of 111 Incorporation of the various pathways into Equation [2.3-20] results in the following equation for a particular organ:
Radioiodines and Particulates Dose Determination Qiwv))
[2.3-21]
.:::: 0.3 mrem (per 31 days), or
.:::: 7.5 mrem (per quarter), or
.:::: 15.0 mrem (per year) where:
R.
= Dose factor for an organ 11-r" for radionuclide "i" for the ground ITG plane exposure pathway (mrem/yr per uCi/sec per m"2).
R.
=
Dose factor for an organ "-r" for radionuclide "i" for l't' M either the cow milk or goat milk pathway (mrem/yr per uCi/sec perm"2).
R.
= Dose factor for an organ 11-r" for radionuclide "i" for the l't' V vegetable pathway (mrem/yr per uCi/sec per m*2).
R.
= Dose factor for an organ 11-r" for radionuclide 11i 11 for the meat l't' B pathway (mrem/yr per uCi/sec per m*2).
R.
= Dose factor for an organ 11-r" for radionuclide "i" for the 1't' I inhalation pathway (mrem/yr per uCi/m3).
It should be noted that Wpv, Wcv, Wvv, Wtv, Wcp, Wdv, and Wwv in Equation
[2.3-21] are in terms ofD/Q(m-2).
Values of the dose factor, Ri,, were calculated using the methodology of NUREG-0133.<3.u.1) The following equations are used for all nuclides, unless specifically listed for tritium or carbon-14:
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'iR of n 1 8.3.2.1.2.2
- Dose Factors For Inhalation Pathway
= mrem/yr per uCi/m3 where:
K'
= A constant of unit conversion (1E6 pCi/uCi).
(BR)a
= The breathing rate of the receptor of age group "a" (m3/yr).
(DF Ai-r)a = Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem/pCi). Inhalation dose factors (DF Ait) by organ for the various age groups are given in Table E-7 through E-10 of Regulatory Guide 1.109, Rev. I <3.u.5) or Tables 5 through 8 of NUREG-0172 <3.13.6> or ERS-LMR-15-006 <3.u.28> for Se-
- 75.
The breathing rates (BR)a used for the various age groups are tabulated below,
- as given in Table E-5 of the Regulatory Guide l.109.<3.n5)
Age Group(a)
Breathing Rate (m3/yr)
Infant 1400 Child 3700 Teen 8000 Adult 8000 8.3.2.1.2.3 Dose Factors For Ground Plane Pathway
= m2 -mrem/yr per uCi/sec where:
K'
= A constant of unit conversion (1E6 pCi/uCi).
K"
= A constant of unit conversion (8760 hr/year).
[2.3-23]
Ai
= The decay constant for the "i" th radionuclide (sec-1).
- t.
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8.3.2.1.2.4 t
SF 11 59of131
= The exposure time (4.73E8 sec or 15 years).
= The groundplane dose conversion factor for organ "t" for the "i" th radionuclide (mrem/hr per pCi/m2). A tabulation ofDFGii: values is presented in Table E-6 of Regulatory Guide 1.109.<3.1.3.5) or ERS-LMR-15-006-<3.1.3.28) for Se-75.
= The shielding factor (dimensionless)'. A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used. <3. I J.5)
Dose Factors For Cow Milk or Goat Milk Pathway
= m2 -mrem/yr per uCi/sec where:
[2.3-24]
K'
= A constant of unit conversion (1E6 pCi/uCi).
QF
= The animal's consumption rate, wet weight (kg/day).
Uap
= The receptor's milk consumption rate, for age "a" (liters/yr).
Yp
= The agricultural productivity by unit area of pasture feed grass (kg/m2).
Ys
= The agricultural productivity by unit area of stored feed (kg/m2).
')
Fm
= The stable element transfer coefficients (days/liter).
r
= Fraction of deposited activity retained on animals feed grass.
(DFLii:)a
= The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem/pCi).
Ingestion dose factors (DFLii:)a for the various age groups are given in Table E-11 through E-14 of Regulatory Guide 1.109<3.u.s) or Tables 1 through 4 ofNUREG-0172
<3-13*6) or ERS-LMR-15-006 <3*13*28) for Se-75.
Ai
= The decay constant for the "i" th radionuclide (sec-1).
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11 60 of 131 Aw
= The decay constant for removal of activity on leaf and plant surfaces by weathering 5.73E-7 sec*1 (corresponding to a 14 day half-life).
tr
= The transport time from pasture, to animal, to milk, to receptor (sec).
th
= The transport time from pasture, to harvest, to animal, to milk, to receptor (sec).
fp
= Fraction of the year that the animal is on pasture (dimensionless).
fs
= Fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless).
Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.109 _(3.1.3.5)
Parameter Value RG. 1.109 Table r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days/liter) each stable element E-1 (cow milk)
E-2 (goat milk)
U ap (liters/yr) - infant 330 E-5 child 330 E-5 teen 400 E-5 adult 310 E-5 (DLFii:)a (mrern/pCi) each radionuclide E-11 to E-14 Yp (kg/m2) 0.7 E-15 Ys (kg/m2) 2.0 E-15 tr(seconds) 1.73E5 (2 days)
E-15 th (seconds) 7.78E6 (90 days)
E-15 Qp (kg/day) 50 E-3 fp 0.5 fs 1.0
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11 61 of 131 For goat's milk, all values remain the same except for QF, which is 6 kg/day.
8.3.2.1.2.5 Dose Factors For Meat Pathway
= m2 -mrem/yr per uCi/sec
[2.3-25]
where:
Fr
= The stable element transfer coefficients ( days/kg).
Uap
= The receptor's meat consumption rate for age "a" (kg/yr).
tr
= The average time from slaughter of meat animal to consumption (sec).
th
- = The transport time from crop field to receptor (sec).
All parameter values are the same as the milk pathway parameter values except Fr which is obtained from Table E-1. Parameter tr is obtained from Table E-15, and Uap is obtained from Table E-5. These values, as obtained from Regulatory Guide 1.109,<3*1.3.S) are as follows:
Parameter Value RG-1.109 Table F (days/kg) each stable element E-1 tr (seconds) l.73E6 (20 days)
E-15 uap (kg/yr) - infant 0
E-5 Child 41 E-5 Teen 65 E-5 Adult 110 E-5 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:
8.3.2.1.2.6 Dose Factors For Vegetation Pathway R
K*[
(r) l (DFL ) [ULF
-il*tL Uas-Fge -ilz*th]
i-rv =
Yv(il.i + ilw) i-r a a/Le l
+
/1
= m2 -mrem/yr per uCi/sec
[2.3-26]
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. f.? of Bl where:
K'
= A constant of unit conversion (1E6 pCi/uCi).
U; = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).
U ~ =The consumption rate of stored vegetation by the receptor in age group "a" (kg/yr).
fL
= The fraction of the annual intake of fresh leafy vegetation grown locally.
fg
= The fraction of the annual intake of stored vegetation grown locally.
tL
= The average time between harvest of leafy vegetation and its consumption (seconds).
th
= The average time between harvest of stored vegetation and its consumption (seconds).
Yv
= The vegetation area density (kg/m2).
all other factors are defined previously.
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109.<3.u.5)
Parameter Value RG-1.109 Table r (dimensionless) 1.0 for radioiodines E-15 0.2 for particulates E-15 (DFLit)a (mrem/pCi) each stable element E-11 to E-14 U ~ (kg/yr) - infant 0
E-5 26 E-5 Child 42 E-5 teen 64 E-5 adult s
0 E-5 U a (kg/yr) - infant child 520 E-5 630 E-5 teen 520 E-5 adult fL (dimensionless) 1.0 E-15
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63 of 131 ODCM: GASEOUS EFFLUENTS Parameter F g (dimensionless) tL (seconds) th (seconds) 2 Yv (kg/m)
Value 0.76 8.6E4 (1 day) 5.18E6 (60 days) 2.0 RG-1.109 Table E-15 E-15 E-15 E-15 As discussed in Section 8.2.2 for tritium, the parameter W for the food pathway is based upon XJQ. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Equation [2.3-20] may be expressed for purposes of implementation of 40 CFR 190, discussed in l/2-0DC-2.04; as follows:
8.3.2.1.2.7 Tritium Dose Equation (X/Q)vvQTvv + (X/Q)tvQTtv + (X/Q)cbQTcb + (X/Q)dvQTdv + (X/Q)wvQTwv]
[23-27]
where:
=
=
=
=
Dose factor for organ "-r" for tritium for the milk pathway (mrem/yr per uCi/m3).
Dose factor for organ "-r" for tritium for the vegetable pathway (mrem/yr per uCi/m3).
Dose factor for organ 11-r" for tritium for the beef pathway (mrem/yr per uCi/m3).
Dose factor for organ "-r" for tritium for the inhalation pathway (mrem/yr per uCi/m3).
Equation [2.3-27] is used to show compliance with 40 CFR 190, as discussed in l/2-0DC-2.04.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RnM is based on I_X/Q]:
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64 of Bl 8.3.2.1.2.8 Tritium Dose Factors For Milk Pathway
= mrem/yr per uCi/m3 where:
K"
= A constant of unit conversion (1000 gm/kg).
H
= Absolute humidity of the atmosphere (8 gm/m3).
0.75
= The fraction of total feed that is water.
[2.3-28]
0.5
= The ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameters and values are the same as for RitM.
The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rtt:v is based on [X/Q]:
8.3.2.1.2.9 Tritium Dose Factors For Vegetation Pathway
= mrem/yr per uCi/m3
[2.3-29]
where all terms have been defined above.
- The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R TtB is based on [X/Q]:
8.3:2.1.2.10 Tritium Dose Factors For Beef Pathway
= mrem/yr per uCi/m3
[2.3-30]
where all terms have been defined above.
(
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65 of 131 11 Carbon-14 dose may be estimated in one of two ways: effluent sampling and calculated doses, or dose calculation based upon reactor characteristics. EPRI document Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" provides the methodology for dose calculation via reactor characteristics. For determining the dose for carbon-14 from an effluent sample progr~m, the following sections apply. The plume and ground pathways are not applicable. The concentration of carbon-14 is based on the airborne concentration rather than the deposition in all pathways. Therefore, the Rcr is based onl_X/Q]. Incorporation of the various pathways into Equation [2.3-20] results in the following equation for a particular organ:
8.3.2.1.2.11 Carbon-14 Dose Determination 3.17E - 8 (PRcTM + pRc-rv + pRcTB + RcT1) [0.5 (X/Q)pvQcpv + (X/Q)cvQccv +
(X/Q)vvQc.,,11 + (X/Q)tvQCtv + (X/Q)cbQccb + (X/Q)dvQcdv + (X/Q)wvQcw.,,]
I NOTE:
[2.3-31]
where:
R
= Dose factor for an organ "-c" for carbon-14 for either the cow C't"M milk or goat milk pathway mrem/yr per uCi/m3).
R
= Dose factor for an organ "-c" for carbon-14 for the vegetable C't"v pathway (mrem/yr per uCi/m3).
R
= Dose factor for an organ "-c" for carbon-14 for the meat C't"B
\\
pathway (mrem/yr per uCi/m3).
R
= Dose factor for an organ "-c" for carbon-14 for the inhalation C't"r pathway (iprem/yr per uCi/m3).
p
= The fractional equilibrium ratio, dimensionless. For batch releases, the parameter p is defined as the ratio of the total annual atmospheric release time to the total annual time during which photosynthesis occurs (assumed to be 4400 *hours).
Under this condition, p should never exceed I. For continuous releases, p = 1.
Because photosynthesis only occurs during daylight hours, it may be acceptable I to take this into further consideration.
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1.1. of Bl 8.3.2.1.2.12 8.3.2.1.2.13 8.3.2.1.2.14 Values of the dose factor, RC'r, were calculated using the methodology of NUREG-0133.<3.1 3.1) Carbon-14 inhalation dose factors were calculated according to Equation [2.3-22] and are therefore not repeated in this section.
The following equations were used for other pathways to determine carbon-14
- dose factors:
Carbon-14 Dose Factors For Cow Milk or Goat Milk Pathway
= mrem/yr per uCi/m3 where:
[2.3-32]
0.11
= The fraction of total plant mass that is natural carbon, dimensionless.
0.16
= The concentration of natural carbon in the atmosphere (g/m3).
and other parameters as defined above.
Carbon-14 Dose Factors For Meat Pathway
= mrem/yr per uCi/m3
[2.3-33]
where all terms have been defined above.
Carbon-14 Dose Factors For Vegetation Pathway
= mrem/yr per uCi/m3
[2.3-34]
where all other terms have been defined above.
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11 67 ofnl The following sections explain the determination of the controlling locations and limits for dose of radioiodines and particulates. While carbon-14 was used to determine controlling locations, there are currently no regulatory limits on carbon-14 effluents from the plant. Equations [2.3-31] though [2.3-34] should be used to calculate dose at the controlling location (0.89 miles NW) for the Annual Radioactive Effluent Release Report.
To show compliance with ODCM CONTROLS 3.11.2.3 and 3.11.2.4, Equation
[2.3-21] is evaluated at the controlling pathway location. For Release Modes 1 through 4, the controlling location is a residence 0.89 miles in the NW sector. Inserting appropriate X/Q values from ATTACHMENT F Tables 2.2-4 to 2.2-10 and D/Q values from ATTACHMENT L Tables 2.3-28 to 2.3-34, Equation [2.3-21] becomes:
8.3.2.1.3 Radioiodines and Particulates {excluding C-14) Dose Determination Qivv + 1.SSE - 8 Qitv + 1.SSE - 8 Qicb + 1.56E - 8 Qidv + 1.56E - 8 Qiwv] + Ri-r:1 [(0.5) 7.30E - 9 Qipv + 2.00E - 5 Qicv + 2.71E - S Qivv
+ 2.22E - 5 Qitv + 2.22E - 5 Qicb + 2.00E - 5 Qidv + 2.00E - S QiwJ
.:s_ 0.3 mrem (per 31 days), or
.:S 7.5 mrem (per quarter), or
,:Sl5.0 mrem (per year)
[2.3-35]
For tritium, for purposes of implementation of 40 CFR 190, as discussed in l/2-0DC-2.04, Equation [2.3-28] reduces to:
3.17E - 8 [Rrrv + Rr-i-1] [(0.5)7.30E - 9 Qivv + 2.00E - 5 Qi;, + 2.71E -5 8.3.2.1.4 Qivv + 2.22E - 5 Qitv + 2.22E - 5 Qicb + 2.00E -
SQidv +
2.00E - 5 Q* ]
lwv
[2.3-36]
Determination of Controlling Location The determination of a controlling locating for implementation of ODCM CONTROLS 3.11.2.3 and 3.11.2.4 for radioiodines and particulates is a function* of:
Radionuclide mix and their isotopic release Release Mode Meteorology Exposure pathway Receptor's age
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"~ of 131 J The incorporation of these parameters into Equation [2.3-19] results in the respective equations for each Release Mode at the controlling location.
In determination of the controlling location for each Release Mode, the radionuclide mix of radio iodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of Release Mode and Release Point. For the 'ground plane exposure pathway, all radionuclides (excluding H-3 and C-14) were considered in determination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling location.
In determination of the controlling location for each Release Mode, all of the exposure pathways, as presented in ATTACHMENT E Table 2.2-3, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations.
For determination of the controlling location, the highest D/Q and X/Q values for each Release Point and Release Mode for the vegetable garden, cow milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and Release Points of ATTACHMENT D Tables 2.2-2a and 2.2-2b Based upon these calculations, it was determined that the controlling location for Release Modes 1 through 4 is the residence (vegetable garden)/child pathway.
For Release Modes 1 through 4, the controlling Release Point and mix is VV-1 and VV-2.
ATTACHMENT J Tables 2.3-2 through 2.3-20 present Ri values for the total body, GI-LLI, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.
These values were calculated using the methodology described in NUREG-OI33(3.l.3.l) using a grazing period of 6 months.
In determination of the controlling location for Release Modes 1-4, ATTACHMENT F Tables 2.2-4 through 2.2-10 are utilized for X/Qs, and ATTACHMENT L Tables 2.3-28 through 2.3-34 are utilized for long term D/Q values. A description of the derivation of the various X/Q and D/Q values is presented in l/2-0DC-3.01.
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8.3.2.2 11 69 r,f 131 Long-term D/Q values for PV-1/2, CV-1, CV-2, VV-1, VV-2, TV-2_, CB-2, DV-2 AND WV-2 are provided for the midpoints of the following distances:
0.0-0.5 mi., 0.5-1.0 mi., 1.0-1.5 mi., 1.5-2.0 mi., 2.0-2.5 mi.,
2.5-3.0 mi., 3.0-3.5 mi., 3.5-4.0 mi., 4.0-4.5 mi., 4.5-5.0 mi.
The values appear in ATTACHMENT K Tables 2.3-21 through.2.3-27. These values may be utilized if an additional special location arises different from those presented in the special locations of ATTACHMENT E Table 2.2-3.
The following relationship must hold for BV-1 or BV-2 to show compliance with ODCM CONTROL 3.11.2.3.
For The Calendar Quarter:
D1.:S 7.5 mrem to any organ For The Calendar Year:
D;;.:S 15 mrem to any organ where:
[2.3-37]
[2.3-38]
D1 = The dose to any organ from radioiodines and particulates (mrem).
The quarterly limits given above represent one-half the annual design objective of Section II.C of Appendix I of 10 CFR 50. If any of the limits of Equations
[2.3-33] and [2.3-34] are exceeded, a Special Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.3.a must be filed with the NRC at the identified locations.
Projection Of Doses (Radioiodines And Particulates)
Doses due to gaseous releases from BV;.1 or BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of radio iodines and particulates will be calculated for use in the 31-day dose projection using Equation [2.3-31]. The 31-day dose projection shall be performed according to the following equations:
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70 of 1 i 1 ODCM: GASEOUS EFFLUENTS 8.4 8.3.2.2.1 When Including Pre-Release Data,
[A+ B]
D31 = -T-. (31) + C
[2.3-39]
8.3.2.2.2 When Not Including Pre-Release Data, D31 = [~] (31) + C
[2.3-40]
where:
D31
= Projected 31 day dose (mrem).
A
= Cumulative dose for quarter (mrem).
B
= Projected dose for this release (mrem).
T
= Current days into quarter.
C
= Value which may be used to anticipate plant trends (mrem).
Gaseous Radwaste System The gaseous radwaste system has the capability to control, collect, process, store, recycle, and dispose of gaseous radioactive waste generated as a result of plant operations, including anticipated operational occurrences.
A simplified flow diagram of the gaseous radwaste system for BV-1 and BV-2 is provided as ATTACHMENT N Figure 2.4-1. A diagram showing the gaseous effluent Release Points is provided as ATTACHMENT P Figure 2.4-2. Since the concept of a shared gaseous radwaste system is used, then gaseous waste generated can be stored, processed, and discharged from either BV-1 or BV-2.
8.4.1 BV-1 Gaseous Radwaste System Components 8.4.1.1 8.4.1.2 8.4.1.3 BR-1EV-2A/2B: Degasifiers There are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
GW-lE-lA/lB: Waste Gas Chillers There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.
GW-1TK-3A thru 3D: Gaseous Waste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of
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8.4.1.4 8.4.1.5 8.4.1.6 8.4.1.7 8.4.1.8 11 71 of nt radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.
GW":"1FL-5A/5B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
GW-lC-lA/lB: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters.
GW-lTK-2: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.
GW-lTK-lA thru lC: Waste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
RM-lGW-108 And RM-lGW-109: Gaseous Effluent Radiation Monitors There are redundant Radiation Monitors on the combined PV-1/2 Gaseous Waste/Process Vent release path. These Radiation Monitors continuously analyze gaseous waste as it is being discharged. Gaseous Monitor RM-1GW-108B is an off-line gamma scintillator, while RM-IGW-109 LRNG is an off-line beta scintillator. The upper activity alarm on the gaseous Channels of these Radiation Monitors have setpoints that would indicate we are approaching the Total Body Dose Rate or Skin Dose Rate limits for radioactive gas leaving the site. If an upper activity alarm on RM-1GW-I08B is received, it automatically terminates the discharge by closing an isolation valve downstream of the Decay Tanks.
8.4.2 BV-2 Gaseous Radwaste System Components 8.4.2.1 8.4.2.2 2BRS-EV21A/21B: Degasifiers There are four Degasifiers (two at Unit 1 and two at Unit 2). They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
2GWS-E21A/21B: Waste Gas Chillers
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. 7?. of li 1 ODCM:. GASEOUS EFFLUENTS 8.4.2.3 8.4.2.4 8.4.2.5 8.4.2.6 8.4.2.7 8.4.2.8 There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the de gasifiers are directed by system pressure to the Waste Gas Chillers.
2GWS-TK22A thru 22D: Waste Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit 1 and four at Unit 2). The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.
2GWS-FLT24A/24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Waste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
2GWS-C21A/21B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters.
2GWS-TK21: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.
2GWS-TK25A thru 25G: Gaseous Waste Storage Tanks There are seven Storage Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Storage Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton-85.
RM-lGW-108 And RM-lGW-109: Gaseous Effluent Radiation Monitors Previously described in Section 8.4.1.
-END-
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73 of 131 ODCM: GASEOUS EFFLUENTS ATTACHMENT A Page 1 of2 GASEOUS SOURCE TERM TABLE 2.1-la 11 BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
RX AUXILIARY CONTAINMENT/
BUILDING SLCRS VENT VENT GASEOUS WASTE/PROCESS VENT Long Tenn, And AUXILIARY MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING CONDENSER/
VACUUM WASTE NUCLIDEC2l BU1LDING0l VENTILATION AIREJECTOR PUMPsC3l SYSTEM Short Tenn Long Tenn Long Tenn Long Tenn Short Term Kr-83m 2.2E-02 4.2E-01 2.7E-01 5.2E-03 0.0 Kr-85m l.SE-01 l.9E+OO l.2E+OO 5.SE-02 7.3E-02 Kr-85 6.lE+0.1 2.SE+OO 1.6E+OO l.OE+Ol 2.3E+02 Kr-87 5.4E-02 l.3E+OO 8.2E-Ol l.lE-02 0.0 Kr-88 2.4E-Ol 3.8E+OO 2.4E+OO 7.0E-02 0.0 Kr-89 4.7E-04 1.2E-01 7.7E-02 4.3E-05 0.0 Xe-13lm 7.4E-01 l.3E-01 8.0E-02 l.8E-01 1.3E+OO Xe-133m 8.9E-Ol 8.9E-01 5.6E-01 3.lE-01 0.0 Xe-133 8.9E+Ol 3.6E+Ol 2.3E+Ol 2.7E+Ol 2.3E+Ol Xe-135m 4.SE-03 3.2E-01 2.0E-01 6.2E-04 0.0 Xe-135 7.0E-01 4.SE+OO 2.8E+OO 2.7E-Ol 0.0 Xe-137 l.OE-03 2.lE-01 l.3E-01 8.8E-05 0.0 Xe-138 l.SE-02 l.lE+OO 6.6E-Ol l.7E-03 0.0 Ar-41 2.SE+Ol 0.0 0.0 0.0 0.0 (I) Containment can be purged via VV-1 (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)
<2) Source Term from BVPS-2 UFSAR Table 11.3.1 <3.1.1.2)
<3) Original Source Term from Calculation No. UR(B)-262 was adjusted for a factor of 14 increase in pump flowrate due to installation of high capacity pumps during 1Rl5. This change in Source Term is documented in Condition Report CR03-04830 and Calculation No. ERS-HHM 014. (3.1.1.5) (3.1.1.8) (3.1.3.10)
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT A Page 2 of2 GASEOUS SOURCE TERM TABLE 2.1-lb 11 BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
SLCRS SLCRS TURBINE UNFILTERED FILTERED BUILDING 74 of 131 PATHWAY PATHWAY VENT GASEOUS WASTE/PROCESS VENT Long Tenn, And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER/
VACUUM WASTE NUCL1DEC2>
BUILDING(!)
VENTILATION VENTILATION AIREJECTOR PUMPSC3>
SYSTEM Short Tenn Long Tenn Long Term Long Term Long Tenn Short Term Kr-83m 4.0E-05 4.2E-Ol 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.4E-02 l.9E+OO l.7E-04 1.2E+OO 3.9E-03 l.2E-02 Kr-85 6.lE+Ol 2.SE+OO 2.3E-04 L6E+OO 7.2E-01 2.3E+02
, Kr-87 5.3E-06 l.3E+OO 1.lE-04 8.2E-01 7.SE-04 0.0 Kr-88 4.lE-03 3.8E+OO 3.SE-04 2.4E+o0 5.0E-03 0.0 Kr-89 0.0 1.2E-01 1.lE-05 7.7E-02 3.lE-06 0.0 Xe-131m 7.2E-01 l.3E-Ol 1.2E-05 8.0E-02 l.3E-02 8.3E-01 Xe-133m 7.6E-01 8.9E-Ol 8.lE-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E+Ol 3.6E+Ol 3.4E-03 2.3E+Ol l.9E-OO 8.2E+OO Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.SE+OO 4.2E-04 2.8E+OO 1.9E-02 0.0 Xe-137 0.0 2.lE-01 2.lE-05 1.3E-01 6.3E-06 0.0 Xe-138 0.0 1.lE+OO 9.7E-05 6.6E-01 l.2E-04 0.0 Ar-41 2.SE+Ol 0.0 0.0 0.0 0.0 0.0 (l) Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)
<2) Source Term from BVPS-2 UFSAR Table 11.3.2(3.1.23)
<3) Source Term from Calculation No. UR(B)-262(3.1.2.5)
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS ATTACHMENT B Page 1 of2 Procedure Number:
l/2-0DC-2.02 Unit:
Level OfUse:
1/2 General Skill Reference Revision:
Page Number:
11 75 of Bl GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2a BV-1 MONITOR DETECTOR EFFICIENCIES GASEOUS WASTE/
Rx CONTAINMENT/
NUCLIDE AUXILIARY BUILDING VENT PROCESS VENT SLCRS VENT PRIMARY ALIERNAIE PRIMARY ALIERNAIE PRIMARY ALIERNAIE MONITOR<1>
MONITOR<2>
MONITOR<2>
MONITOR<1l MONITOR<1>
MONITOR<2>
RM-VS-109 RM-VS-IOIB RM-GW-108B RM-GW-109 RM-VS-110 RM-VS-107B LRNG (cpm/uCi/cc)
(cpm/uCi/cc)
LRNG LRNG (cpm/uCi/cc)
( cps/uCi/cc)
(cps/uCi/cc)
( cps/uCi/cc)
Kr-83m Kr-85m 1.14 ES 7.16 E7 9.00E7 1.14 ES 1.14E5 4.92E7 Kr-85 1.14 ES 8.59 E7 3.56 E5 1.14 ES 1.14 E5 5.91 E7 Kr-87 1.77 ES 1.12 E8 6.78 E7 1.77 E5 1.77 ES 7.72E7 Kr-88 1.05 ES 6.86 E7 1.05 E8 1.05 E5 1.05 ES 4.72E7 Kr-89 1.89 ES 8.81 E7 1.28 E8 1.89 ES 1.89 ES 6.06 E7 Kr-90 1.89 E4 1.12 E8 1.23 E8 1.89 E4 l.89E4 7.72E7 Xe-13lm 7.22E4 5.89 E4 2.07E6 7.22 E4 7.22E4 4:05 E4 Xe-133m 1.28 ES 9.60 E5 1.16 E7 1.28 ES 1.28 ES 6.61 ES Xe-133 4.39 E4 3.05 E7 9.24E6 4.39 E4 4.39 E4 2.10 E7 Xe-135m 3.28 E4 1.43 E7 6.58 E7 3.28 E4 3.28 E4 9.85 E6 Xe-135 1.37 ES 9.04E7 1.03 E8 1.37 ES 1.37 ES 6.22E7 Xe-137 1.83 ES 1.16 E8 2.91 E7 1.83 ES 1.83 ES 7.98 E7 Xe-138 1.43 ES 8.98 E7
.1.06 E8 1.43 ES 1.43 E5 6.18 E7 Ar-41 1.60 E5 9:51 E7 6.59 E7 1.60 ES 1.60 E5 6.56 E7 (I) Efficiencies from Calculation Package ERS-SFL-85-031. <3. i.1.4)
(2) The listed detector efficiencies for the respective alternate monitors (Victoreen) are corrected for the reduced pressures observed and documented during operation.
- t t
\\0
Beaver Valley Power Station Procedure Number:
Title:
ODCM: GASEOUS EFFLUENTS ATTACHMENT B Page 2 of2 Unit:
1/2 Revision:
11 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
76 {)f131 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1.. 2b BV-2 MONITOR DETECTOR EFFICIENCIES
( cprn/uCi/cc)
SLCRS SLCRS WASTE GAS UNFILTERED FILTERED STORAGE DECON NUCLIDE0l PATHWAY PATHWAY VAULTVENT BUILDING VENT 2HVS-RQ10IB 2HVS-RQ109B 2RMQ-RQ303B 2RMQ-RQ301B Kr-83m Kr-85m 3.20E7 5.83E7 3.20E7 3.20E7 Kr-85 3.60E7 7.19E7 3.60E7 3.60E7 Kr-87 3.73E7 8.85E7 3.73E7 3.73E7 Kr-88 3.05E7 6.80E7 3.05E7 3.05E7 Kr-89 3.72E7 8.73E7 3.72E7 3.72E7 Kr-90 3.86E7 8.80E7 3.86E7 3.86E7 Xe-131m 2.44E7 4.61E4 2.44E7 2.44E7 Xe-133m 2.86E7 6.06E4 2.86E7 2.86E7 Xe-133 l.80E7 2.94E7 1.80E7 l.80E7 Xe-135m
- 7.22E6 l.55E4 7.22E6 7.22E6 Xe-135 3.86E7 7.48E7 3.86E7 3.86E7 Xe-137 3.78E7 9.07E7 3.78E7 3.78E7 Xe-138 3.52E7 7.74E7 3.52E7 3.52E7 Ar-41 3.79E7 7.90E7 3.79E7 3.79E7 (I)
Efficiencies from Calculation Package ERS-SFL-86-026.<3.1.2.i)
,.:i
- i
\\C
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Nwnber:
11 77 of 111 ATTACHMENT C Page 1 of 1 DELETED
(>
\\
Table 2.2-1
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS ATTACHMENT D Page 1 of 2 RADIONUCLIDE MIX TABLE 2.2-2a Procedure Number:
l/2-0DC-2.02 Unit:
Level OfUse:
1/2 General Skill Reference Revision:
Page Number:
11 78 of 131 BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
RX CONTAINMENT/
AUXILIARY SLCRSVENT BUILDING VENT GASEOUS WASTE/PROCESS VENT Long Term, And AUXILIARY MAIN CONTAINMENT CONTAINMENT BUILDING CONDENSER/
VACUUMM GASEOUS NUCLIDE<2l BUILDINGOl VENTILATION AIR EJECTOR PUMPs<3l WASTE SYSTEM Short Term Long Term Long Term Long Term Short Term Kr-83m 2.2E-02 4.2E-01 2.7E-01 5.2E-03 0.0 Kr-85m l.5E-01 l.9E+OO l.2E+OO 5.5E-02 1.2E-02 Kr-85 6.lE+Ol 2.5E+OO l.6E+OO l.OE+Ol 2.3E+02 Kr-87 5.4E-02 1.3E+OO 8.2E-01 l.lE-02 0.0 Kr-88 2.4E-01 3.8E+OO 2.4E+OO 7.0E-02 0.0 Kr-89 4.7E-04 l.2E-01 7.7E-02 4.3E-05 0.0 Xe-131m 7.4E-01 1.3E-01 8.0E-02 l.8E-01 8.3E-01 Xe-133m 8.9E-01 8.9E-01 5.6E-Ol 3.lE-01 0.0 Xe-133 8.9E+Ol 3.6E+Ol 2.3E+Ol 2.7E+Ol 8.2E+OO Xe-135m 4.5E-03 3.2E-01 2.0E-01 6.2E-04 0.0 Xe-135 7.0E-01 4.5E+OO 2.8E+OO 2.7E-Ol 0.0 Xe-137 l.OE-03 2.lE-01 1.3E-01 8.8E-05 0.0 Xe-138 l.5E-02 l.lE+OO 6.6E-01 l.7E-03 0.0 I-131 l.2E-03 4.6E-02 2.lE-02 6.6E-03 0.0 I-132 0.0 0.0 0.0 3.5E-05 0.0 I-133 2.0E-04 6.7E-02 3.0E-02 l.2E-03 0.0 I-134 0.0 0.0 0.0 6.6E-06 0.0 I-135 0.0 0.0 0.0 2.0E-04 0.0 Co-58 7.5E-04 6.0E-02 0.0 2.2E-04 0.0 Co-60 3.4E-04 2.7E-02 0.0 l.OE-04 0.0 Mn-54 2.2E-04 l.8E-02 0.0 6.9E-05 0.0 Fe-59 7.5E-05 6.0E-03 0.0 2.2E-05 0.0
- Sr-89 l.7E-05 1.3E-03 0.0 5.2E-06 0.0 Sr-90 3.0E-06 2.0E-04 0.0 9.2E-07 0.0 Cs-134 2.2E-04 1.8E-02 0.0 6.9E-05 0.0 Cs-137 3.8E-04 3.0E-02 0.0 l.2E-04 0.0 C-14 l.OE+OO 0.0 0.0 0.0 7.0E+OO Ar-41 2.5E+Ol 0.0 0.0 0.0 0.0 (1) Containment can be purged via VV-1 (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)
(2) Source Term from BVPS-2UFSAR Table 11.3-1 (3.1.1.2)
(3) See Note <3l from ATTACHMENT A Table 2.1-la (3.1.1.s)(3.1.1.sJc3.Hio)
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 79 of 1
~ 1 ATTACHMENT D Page 2 of2 RADIONUCLIDE MIX TABLE 2.2-2b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
SLCRS SLCRS UNFILTERED FILTERED TURBINE PATHWAY PA1HWAY BUILDING VENT GASEOUS WASTE/PROCESS VENT Long Tenn, And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER/
VACUUM WASTE NUCLIDE<2)
BUILDING(!)
VENTILATION VENTILATION AIREJECTOR PUMPs<3>
SYSTEM Short Tenn Long Tenn Long Tenn Long Tenn Long Tenn Short Tenn Kr-83m 4.0E-05 4.2E-01 3.9E-05 2.7E-Ol 3.7E-04 0.0 Kr-85m 1.4E-02 l.9E+OO I.7E-04 1.2E+OO 3.9E-03 1.2E-02 Kr-85 6.lE+Ol 2.SE+OO 2.3E-04 l.6E+OO 7.2E-01 2.3E+02 Kr-87 5.3E-06 1.3E+OO l.IE-04 8.2E-Ol 7.SE-04 0.0 Kr-88 4.lE-03 3.8E+OO 3.SE-04 2.4E+OO 5.0E-03 0.0 Kr-89 0.0 l.2E-01 l.lE-05 7.7E-02 3.IE-06 0.0 Xe-131m 7.2E-Ol l.3E.-Ol l.2E-05 8.0E-02 l.3E-02 8.3E-Ol Xe-133m 7.6E-01 8.9E-Ol 8.lE-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E+Ol 3.6E+Ol 3.4E-03 2.3E+Ol l.9E-OO 8.2E+OO Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.SE+OO 4.2E-04 2.8E+OO l.9E-02 0.0 Xe-137 0.0 2.lE-01 2.lE-05 l.3E-01 6.3E-06 0.0 Xe-138 0.0 l.lE+OO 9.7E-05 6.6E-01 1.2E-04 0.0 1-131 2.7E-05 4.6E-03 6.SE-04 2.lE-02 4.7E-04 0.0 1-132 0.0 0.0 0.0 0.0 2.SE-06 0.0 1-133 2.6E-06 6.7E-03 8.7E-04 3.0E-02 8.4E-05 0.0 1-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 1-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co~58 7.SE-02 6.0E-04 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-02 2.7E-04 0.0 0.0 7.4E-06 0.0 Mn-54 2.2E-02 l.SE-04 0.0 0.0 4.9E-06 0.0 Fe-59 7.SE-03 6.0E-05 0.0*
0.0 1.6E-06 0.0 Sr-89 1.7E-03 1.3E-05 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-04 2.0E-06 0.0 0.0 6.6E-08 0.0 Cs-134 2.2E-02 l.SE-04 0.0 0.0 4.9E-06 0.0 Cs-137 3.SE-02 3.0E-04 0.0 0.0 8.4E-06 0.0 C-14 1.0E+OO 0.0 0.0 0.0 0.0 7.0E+OO Ar-41 2.5E+Ol 0.0 0.0 0.0 0.0 0.0
(!) Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)
(2) Source Term from BVPS-2UFSAR Table 11.3-2<3* I.1.3)
(3) See Section 8.1.1.1
TABLE2.2-3 DISTANCES OF LIMITING MAXIMUM INDIVIDUAL RECEPTORS TO RELEASE POINTS FOR ANNUAL X/Q VALUES DOWNWIND SITEBOUNDARY*
VEGETABLE GARDEN (meters)
MILK COW MILK GOAT MEAT ANIMAL RESIDENT SECTOR GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV N
NNE NE ENE E
WNW NW NNW (1)
(2) 670 535 490 490 545 575 575 655 850 975 1,435 595 685 810 655 645 579 792 442 448 546 607 701 762 887 1,064 1,439 561 640 701 567 558 413 632 327 394 551 672 815 912 1,054 1,226 1,574 660 681 676 482 420 2,623 2,740 724 1,674 1,979 1,577 1,835 1,738 3,138 2,317 2,221 2,301 3,556 3,605 1,464 1,464 2,423 2,461 901 1,658 1,922 1,619 1,961 1,933 3,372 2,560 2,439 2,463 7,741 7,065 5,729 5,053 3,347 3,347 5,182 3,635 5,118 3,590 4,538 1,415 1,285 7,526 6,998 5,848 5,244 3,539 3,590 5,341 4,651 6,276 20,760 6,824 4,265 2,865 5,729 9,977 5,616 2,993 5,195 4,521 22,529 10,944 15,450 4,418 6,033 20,545 6,671 4,200 2,899 5,848 10,166 5,859 3,210 22,507 10,832 15,262 4,152 2,848 7,741 4,265 1,577 3,299 1,770 2,253 2,317 2,414 2,446 4,088 3,605 4,570 3,959 3,919 2,605 7,526 4,200 1,619 3,420 1,964 2,487 2,560 2,632 2,608 4,166 3,590 4,461 3,774 2,527 2,639 708 708 756 1,577 1,835 1,432 2,189 1,223 2,221 2,301 3,556 3,605 1,432 1,143 2,295 2,461 790 1,562 1,922 1,650 1,961 1,628 2,423 1,466 2,439 2,463 3,635 3,590 1,383 1,253
- Distances for ground releases are measured from the center point between the BV-1 and BV-2 Containment Buildings. Distances for elevated release are measured from the BV-1 Cooling Tower. Elevated release is applicable to PV-1/2. Ground release is applicable to all other release points.
(1) TV-2 and CB-2 (2) VV-1, CV-1, VV-2, CV-2, DV-2, WV-2
0
. ::l TABLE2.2-4 u
~
CV-1 AND CV-2 ANNUAL AVERAGE, GROUND LEVEL, n
X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES
~
(IDENTIFIED IN_ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS
~
3 (lE-7 sec/m )
(I')
to tr:1 0
('I)
INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES e
~
(I')
tr:1
('I)
'Tl
~
DOWN-SITE VEGE-
'Tl WIND BOUND TABLE MILK MILK MEAT RESI-0-
0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-t"""
SECTOR
-ARY GARDEN cow GOAT ANIMAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 e
~
~
0 I
--:3
('I)
N 125.0 12.80 5.360 6.27 13.50
. 233.0 39.5 18.70 11.80 7.68 5.82 4.240 3.480 2.660 2.280 Vi (I')
NNE 50.2 6.92 2.040 6.42 7.16 148.0 26.8 10.80 6.62 4.60 3.44 2.690 2.190 1.830 1.560
~
~
NE 102.0 47.40 1.200 0.265 1.20 49.10 120.0 21.6 11.60 6.99 4.81 3.55 2.370 1.910 1.450 1.230 F
0 ENE 85.8 12.50 0.124 42.20 103.0 18.4 9.55 5.70 4.14 3.04 2.340 1.880 1.260 1.060 tr:1
~
u
('I)
~~~
"""t E
54.5 6.16 0.807 1.910 1.91 32.60 89.5 15.7 6.08 3.65 2.49 1.83 1.300 1.040 0.859 0.726 Cl'.l
- ,OOQ n ESE 31.l 6.92 3.010 6.92 6.92 59.1 10.5 5.16 3.10 1.95 1.43 1.020 0.815 0.612 0.517 (I') G i
~
SE 27.8 6.70 0.994 0.994 2.74 6.70 65.9 12.0 5.89 3.54 2.41 1.77 1.160 0.931 0.768 0.649 00 SSE 24.1 6.68 1.030 0.372 6.50 9.01 67.2 12.0 5.46 3.30 1.91 1.41 0.997 0.803 0.665 0.563 0
z Hi
- t "O -....) z
~ ~
s 27.5 3.40 3.090 --
5.57 5.81 99.9 17.5 6.77 4.11 2.84 2.10 1.490 1.200 0.999 0.848 SSW 23.8 6.31 3.700 1.740 6.31 19.30 110.0 19.9 7.83 4.80 3.33 2.48 1.940 1.580 1.190 1.020
~
SW 22.3 13.90 9.050 12.30 13.90 160.0 29.2 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 tr:1 WSW 163.0 19.30 5.720 --
17.70 19.30 283.0 49.8 23.50 14.60 10.30 7.72 5.690 4.650 3.620 3.090
~
(I')
~
~
i w
218.0 15.70 9.540 13.00 15.70 615.0 103.0 49.00 31.00 15.40 11.70 9.320 7.660 6.460 5.550
< t,-,-
()
~;:
40'.70
-~ 10 C.
WNW 487.0 30.100 1.810 40.70 40.70 1290.0 203.0 92.10 59.20 40.60 31.20 25.000 20.700 14.200 12.200 C:
NW 924.0 194.00 -
8.660 40.50 200.00 1710.0 262.0 123.00 79.80 55.00 42.30 34.000 28.200 19.400 16.700 z
NNW 302.0 63.00 1.720 15.40 92.30 547.0 86.4 40.80 26.20 17.60 13.50 10.100 8.350 6.560 5.660 t::: a i Cl~ Ng° I
0
< o**
z
- i g_ u I:!: 0
~c: I>'..., (j
..... g. -c:: tG C/l "'
- -! s~ 0 Hi N
~
~ ;,..
0 ::i 0 0
TABLE2.2-5 0
- i.
t,
~
VV-1 AND VV-2 ANNUAL AVERAGE, GROUND LEVEL, n
X/Q VALVES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCA TJONS
~
3 (IE-7 sec/m )
r;JJ t:o tr:l INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES 0
('I)
C:
~
r;JJ tr:l
('I)
'T'.I
""'I DOWN-SITE VEGE-
'T'.I WIND BOUND TABLE MILK MILK MEAT RESI-0-
0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-I:""'
SECTOR
-ARY GARDEN COW GOAT ANIMAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0
~
~
0 I
>-:l
~
N 152.0 15.00 5.980 7.06 15.90 276.0 49.9 22.70 13.70 8.75 6.52 4.69 3.810 2.900 2.470 VI r;JJ NNE 62.3 7.66 2.150 7.08 7.95 189.0 32.0 12.20 7.31 4.99 3.69 2.87 2.320 1.920 1.630 a;:
""ti NE 132.0 57.90 1.240 0.269 1.24 60.20 156.0 24.8 7.51 5.09 3.73 2.47 1.980 1.500 1.270 -
12.70 I:""'
0 ENE 110.0 13.60 1.270 50.40 135.0 20.6 10.20 6.01 4.31 3.14 2.41 1.930 1.290 1.080 tr:l
~
t,
('I) r;JJ
>-:l
""'I E
67.8 6.66 0.828 1.990 1.99 38.80 116.0 17.7 6.57 3.86 2.61 1.90 1.34 1.070 0.883 0.774
'"C '"C >-:l C/J.
~ Pl > \\
r-+-
ESE 38.0 7.64 3.200 7.64 7.64 76.7 11.9 5.59 3.29 2.05 1.49 1.05 0.842 0.630 0.531 oo ~ n a
SE 33.3 7.27 1.030 1.030 2.88 7.27 86.2 13.5 6.37 3.75 2.53 1.84 1.20 0.960 0.790 0.666
-N::i::
SSE 29.1 7.41 1.080 0.382 7.19 10.10 87.0 13.7 5.98 3.53 2.02 1.48 1.04 0.833 0.688 0.531
~~~
0
'"C -..J z
~
I
>-:l s
32.8 3.65 3.300 6.10 6.38 127.0 20.3 7.56 4.48 3.04 2.23 1.57 1.260 1.050 0.885
'T'.I SSW 28.7 7.08 4.040 1.850 7.08 22.90 140.0 23.6 8.87 5.28 3.60 2.66 2.07 1.670 1.260 1.070 SW 26.2 15.70 9.980 13.80 15.70 204.0 34.8 18.40 11.40 6.38 4.71 3.66 2.960 2.230 1.900
~
WSW 201.0 22.40 6.230 --
20.40 22.40 347.0 61.3 27.70 16.60 11.40 8.49 6.19 5.020 3.880 3.300
~
r;JJ c
345.0
~ ~ ~-
0 w
18.00 10.600 --
14.70 18.00 715.0 132.0 60.30 36.50 17.70 13.20 10.40 8.440 7.060 6.040 r,
\\.-,.t. rn*
WNW 598.0 48.60 35.000 1.920 48.60 48.60 1410.0 269.0 120.00 73.00 48.50 36.40 23.400 15.900 13.600
- ..... ~- N
- 0.
28.70
~
NW 1030.0 262.00 9.520 47.80 271.00 1820.0 350.0 164.00 100.00 66.60 50.10 39.50 32.300 21.900 18.800 z
NNW 345.0 83.40 1.840 18.10 121.00 601.0 114.0 52.80 32.20 21.00 15.80 11.60 9.460 7.360 6.310 t::'. § i 0~ Ncr I
~
G < 0..
z :::s !!. t,
~ Q 00 § ac n N<:r
~
"' en"'
0
- >;"' ~
0 Pi = N i,.......
~
w
~
cil
- s
(")
G
0 a:
TABLE2.2-6 t:i
~
PV-1/2 ANNUAL A VERA GE, ELEVATED LEVEL, X/Q VALUES
(;
~
FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS C) 3 (IE-7 sec/m)
CZ) to tn 0
(1)
INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES C
~
CZ) tn (1)
'Tl
~
DOWN-SITE VEGE-
'Tl r
WIND BOUND TABLE MILK MILK MEAT RESI-0-
0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-C
~
SECTOR
-ARY GARDEN cow GOAT ANIMAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0
~ --
0 (1)
I
>--3 V,
~
N 0.0082 6.720 1.910 2.27 6.790 0.0289 23.1000 8.2700 5.32 2.56 1.91 1.480 1.200 0.996 0.846
~
CZ)
NNE 0.0280 6.690 1.430 6.14 6.890 0.0175 14.5000 6.9800 5.47 3.27 2.69 1.770 1.430 1.290 1.100
~
NE 0.0110
.074 1.610 0.350 1.61 0.055 0.0069 0.1160
.2300 7.10 5.38 3.68 2.880 2.090 1.880 1.570 r
0 ENE 0.0110 9.090 1.770 0.525 0.0135 0.3310 7.2800 6.02 4.75 3.22 2.620 2.030 1.710 1.100 tn
~
t:i -
(1)
~~~
~
(/)
E 0.0360 8.300 1.240 2.870 2.87 8.300 0.0124 17.1000 7.8600 6.20 3.67 2.83 2.190 1.730 1.280 1.200
- ,;:, (JQ n f"'+,
ESE 0.0420 11.600 4.570 11.60 11.200 0.0208 12.7000 8.1400 4.78 3.00 2.20 1.360 1.160 0.830 0.737 CZ) 0
~
~
l,.)
SE 0.0750 7.890 1.230 1.230 3.05 7.890 0.4770 7.4000 7.5700 4.45 2.79 2.05 1.460 1.180 0.811 0.686 00 0
SSE 0.2060 7.390 1.160 0.357 7.20 9.770 0.3030 9.4400 6.9300 4.06 2.58 1.89 1.170 0.937 0.646 0.546 z >-+i
~
""o.....:i z
>--3 I "rj s
5.740 3.760 3.490 --
6.06 6.310 0.7960 8.5100 8.4900 4.98 3.37 2.47 1.380 1.110 0.774 0.655 SSW 7.640 3.610 2.140 0.872 3.61 5.820 26.1000 9.1000 4.0300 3.11 2.11 1.56 1.030 0.834 0.807 0.684 SW 6.500 3.900 2.560 3.47 3.900 36.1000 15.9000 4.9300 3.12 1.77 1.57 1.201 1.060 1.150 0.977 ti1 WSW 0.126 4.350 1.420 --
3.98 4.350 0.3870 17.8000 4.9000 3.53 2.36 1.64 1.460 1.210 0.920 0.781 CZ)
C
~
- s. ~;:;*
,_.., !1.
w 0.029 2.490 0.764 2.02 2.490 0.0147 8.7200 6.2300 3.68 2.50 1.84 0.741 1.120 0.851 0.795
\\-, 0 i0 s:,.
C:
?.
WNW 0.033 2.530 1.780 0.163 2.53 2.530 0.0202 0.0549 0.0809 3.07 2.50 1.84 1.llO 0.686 0.791 0.731 z
NW 0.007 0.074 0.305 1.67 0.073 0.0084 0.0650 0.1170 3.66 2.30 1.69.1.210 0.903 0.804 0.683 sf NNW 0.008 6.460 0.224 1.81 6.590 0.0135 6.7800 5.0200 2.96 1.93 1.49 1.050 0.849 0.705 0.599 i
C) \\;
I (1)
~ 0..
z ::s - t:i
~ ~
- Elevated release X/Q value at site boundary location where ground level release X/Qs maximize.
~! ~c:: n
" ~~
~
0 0
'"+)
N
- ,
- :i w
(1)
~
(1)
- s 0
(1)
0 g
TABLE2.2-7 t:l
!'I!
n TV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES
~
FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS
~
3 (lE-7 sec/m)
Cl.)
to tr:1 0
('!)
INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES e
~
Cl.)
tr:1
('!)
>Tj I-I DOWN-SITE VEGE-
>Tj t'""
WIND BOUND TABLE MILK MILK MEAT RESI-0-
0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-
~
~
SECTOR
- ARY GARDEN COW GOAT ANIMAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 0
~
I
'""'3 V,
N 105.0 14.00 5.740 6.74 14.80 244.0 42.6 20.50 12.70 8.18 6.15 4.45 3.640 2.770 2.380
~
Cl.)
NNE 102.0 7.37 2.130 6.83 7.64 161.0 28.8 11.40 6.94 4.79 3.56 2.78 2.250 1.870 1.590
'"'O NE 96.6 51.90 1.230 0.268 1.23 53.80 132.0 23.0 12.10 7.24 4.95 3.64 2.42 1.950 1.480 1.250 p
0 tr:1
~
ENE 84.1 13.20 1.280 46.30 115.0 19.4 9.89 5.85 4.23 3.09 2.38 1.900 1.270 1.070 t:l -
(D
~ '""C ~
I-I (I'_)
E 60.7 6.49
.829 1.980 1.98 35.70 99.2 16.6 6.32 3.75 2.55 1.87 1.32 1.060 0.871 0.735
~ p) >
g ESE 37.1 7.25 3.100 7.25 7.25 65.8 11.1 5.36 3.19 2.00 1.46 1.03 0.829 0.621 0.524 oo ~ n 2.47 1.81 1.18 0.945 0.779 0.658
.i:,. ::r:
~*
SE 41.8 7.06 1.020 1.020 2.85 7.06 73.5 12.6 6.12 3.64 00~
0 SSE 34.0 7.16 1.070 0.384 6.96 9.69 74.2 12.7 5.71 3.41 1.97 1.45 1.02 0.818 0.676 0.572 z >-+, tr:1
~
'""C -....J z
'""'3 s
32.7 3.64 3.310 --
6.00 6.27 109.0 18.6 7.13 4.29 2.94 2.17 1.53 1.230 1.020 0.866
~
>Tj SSW 29.7 6.73 3.890 1.800 6.73 20.90 120.0 21.3 8.31 5.03 3.46 2.57 2.00 1.620 1.230 1.040 tr:1 SW 24.1 14.80 9.550 13.10 14.80 174.0 31.2 17.20 10.40 6.10 4.54 3.54 2.870 2.170 1.850
'""'3 WSW 159.0 20.80 6.010 --
19.10 20.80 301.0 53.6 25.30 15.60 10.80 8.09 5.93 4.830 3.750 3.200
~
Cl.)
C:
~ ~~-
0 0
...... §:
(>
N
- 0.
w 264.0 16.90 10.100 --
13.90 16.90 636.0 111.0 53.90 33.50 16.50 12.40 9.82 8.040 6.760 5.790
-~
~
WNW 404.0 44.50 32.500 1.870 44.50 44.50 1310.0 218.0 104.00 65.40 44.20 33.60 26.70 22.000 15.000 12.900 z
NW 735.0 216.00 9.100 43.90 222.00 1720.0 279.0 140.00 88.80 60.30 45.90 36.60 30.100 20.600 17.700
~§ NNW 247.0 71.00 1.820 17.00 99.40 557.0 924.0 45.90 28.90 19.20 14.60 10.80 8.880 6.950 5.980
- i
- , 0~ No-I
!l
~ (1) < o**
z
- i g_ t:l
~Q
~~ !:?.. C: n I
(>
~~
N 0
0 f+-i N
~
w
~
(1)
- i 0
(1)
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Leyel OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT F Page 5 of7 0-5 MILE DISPERSION PARAMETERS TABLE2.2-8 11 DV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES 85 of 111 (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (lE-7 sec/m3)
Same as Table 2.2-4
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT F Page 6 of7 0-5 MILE DISPERSION PARAMETERS TABLE2.2-9 11 WV-2 ANNUAL AVERAGE,.GROUND LEVEL, X/Q VALVES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES
~6 of 111 (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (lE-7 sec/m3)
Same as Table 2.2-4
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT F Page 7 of7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-10 11 CB-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES 87 of 131 (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS Same as Table 2.2-7
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 88 of Bl ATTACHMENT G Page 1 of2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Ki Li Mi Ni TOTAL BODY SKIN DOSE GAMMA AIR BETA AIR DOSE NUCLIDE(!)
DOSE FACTOR FACTOR DOSE FACTOR FACTOR mrem/yr mrem/yr mrad/yr mrad/yr Per Per Per Per uCi/m3 uCi/m3 uCi/m3 uCi/m3 Kr-83m 7.56E-02 l.93E+Ol 2.88E+02 Kr-85m l.17E+03 l.46E+03 l.23E+03 l.97E+03 Kr-85 l.61E+Ol 1.34E+03 l.72E+Ol l.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 l.03E+04 Kr-88 l.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 l.66E+04 l.OIE+04 l.73E+04 l.06E+04 Kr-90 l.56E+04 -
7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+Ol 4.76E+02 l.56E+02 I.l1E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 l.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.l 1E+02 3.36E+03 7.39E+02 Xe-135 l.81E+03 l.86E+03 l.92E+03 2.46E+03 Xe-137 l.42E+03 l.22E+04 l.51E+03 l.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 (1) The listed dose factors are for radionuclides that may be detected in gaseous effluents.
I
Beaver Valley Power Station Procedure Number:
I/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 R9 of Bl ATTACHMENT G Page2 of2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS
/
TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES V/1)
B/J),(2) vP)
BP)
TOTAL BODY GAMMA AIR TOTAL BODY GAMMAAIR NUCLIDE<4)
DOSE FACTOR DOSE FACTOR DOSE FACTOR DOSE FACTOR mrem/yr mrad/yr mrem/yr mrad/yr Per Per Per Per uCi/sec uCi/sec uCi/sec uCi/sec Kr-83m 3.19E-10 l.75E-8 4.58E-8 3.96E-5 Kr-85m 7.81E-5 l.16E-4 4.70E-4 7.06E-4 Kr-85 l.55E-6 2.35E-6 5.54E-6 8.40E-6 Kr-87 5.13E-4 7.74E-4 1.45E-3 2.19E-3 Kr-88 l.39E-3 2.09E-3 4.09E-3 6.16E-3 Kr-89 7.99E-4 1.20E-3 l.25E-3 l.88E-3 Xe-131m l.64E-5 2.47E-5 l.67E-4 3.09E-4 Xe-133m 1.38E-5 2.1 lE-5 l.32E-4 2.61E-4 Xe-133 l.05E-5 1.56E-4 l.54E-4 2.76E-4 Xe-135m 2.41E-4 3.66E-4 6.21E-4 9.50E-4 Xe-135 l.41E-4 2.12E-4 6.96E-4 l.05E-3 Xe-137 6.00E-5 9.05E-5 9.66E-5 l.46E-4 Xe-138 8.1 IE-4 1.22E-3 2.22E-3 3.34E-3 Ar-41 l.02E-3 l.53E-3 2.68E-3 4.02E-3 (I) Vi and Bi values used to implement Modes 1, 2, and 3 of Section 2.2.1 (1 OCFR20)
(2) Bi values used to implement Moqes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50)
(3) Vi and Bi values to implement Mode 4 of Section 2.2.1 (1 OCFR20) and to implement monitor setpoint determinations of Section 2.1.2 and 2.1.4 (4) The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I I
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 90 of 131 ATTACHMENT H Page 1 of 1 ORGAN DOSE PARAMETERS Table 2.2-13 p; T VALUES FCR A CHI LD FCR THE BEAVER VALLEY SI TE
( rrr em' yr per ua / cu rret er)
Nuclide Bone Liver T. Body Thyroid Ki dney Lung GI - LLI 1 H-3 O.OOE+OO 1.12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03 2 C-14
- 3. 59E+04
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03 3 P-32
- 2. 60E+06
- 1. 14E+05
- 9. 88E+04 O.OOE+OO 0.00E+OO
- 0. OOE+OO 4.22E+04 4 Cr-51
- 0. OOE+OO O.OOE+OO
- 1. 54E+02 8.55E+01 2.43E+01
- 1. 70E+04 1.08E+03 5 Ml-54 O.OOE+OO
- 4. 29E+04
- 9. 51 E+03
- 0. OOE+OO
- 1. OOE+04
- 1. 58E+06
- 2. 29E+04 6 Fe-59 2.07E+04
- 3. 34E+04
- 1. 67E+04 O.OOE+OO O.OOE+OO
- 1. 27E+06 7.07E+04 7 Co-57 O.OOE+OO 9.03E+02
- 1. 07E+03 O.OOE+OO O.OOE+OO 5.07E+05 1.32E+04 8 Co-58 O.OOE+OO
- 1. 77E+03
- 3. 16E+03
- 0. OOE+OO
- 0. OOE+OO
- 1. 11 E+06 3.44E+04 9 Go-60 O.OOE+OO
- 1. 31E+04 2.26E+04 O.OOE+OO
- 0. OOE+OO 7.07E+06 9.62E+04 10 Zn-65 4.26E+04
- 1. 13E+05
- 7. 03E+04 O.OOE+OO
- 7. 14E+04 9.95E+05
- 1. 63E+04 11 Se-75
- 0. OOE+OO
- 4. 40E+03
- 2. 17E+03 O.OOE+OO
- 5. 11E+03 6.33E+05 1.69E+04 12 Rb-86 O.OOE+OO 1.98E+05
- 1. 14E+05
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 7. 99E+03 13 Sr-89
- 5. 99E+05
- 0. OOE+OO
- 1. 72E+04 O.OOE+OO O.OOE+OO
- 2. 16E+06
- 1. 67E+05 14 Sr-90
- 1. 01E+08
- 0. OOE+OO
- 6. 44E+06 O.OOE+OO
- 0. OOE+OO
- 1. 48E+07 3.43E+05 15 Y-91
- 9. 14E+05
- 0. OOE+OO
- 2. 44E+04 O.OOE+OO
- 0. OOE+OO 2.63E+06
- 1. 84E+05 16 Zr-95
- 1. 90E+05
- 4. 18E+04
- 3. 70E+04 O.OOE+OO 5.96E+04 2.23E+06
- 6. 11E+04 17 Nb-95 2.35E+04
- 9. 18E+03
- 6. 55E+03 O.OOE+OO 8.62E+03
- 6. 14E+05
- 3. 70E+04 18 Nb-97
- 4. 29E- 01
- 7. 70E- 02
- 3. 60E- 02 O.OOE+OO
- 8. 55E-02 3.42E+03
- 2. 78E+04 19 rv'b-99 O.OOE+OO
- 1. 72E+02
- 4. 26E+01 O.OOE+OO 3.92E+02 1.35E+05 1.27E+05 20 Tc-99m
- 1. 78E-03
- 3. 48E-03
- 5. 77E-02 O.OOE+OO
- 5. 07E 9.51E+02 4.81E+03 21 Ru-103
- 2. 79E+03 O.OOE+OO
- 1. 07E+03 0.00E+OO 7.03E+03 6.62E+05 4.48E+04 22 Ru-106
- 1. 36E+05 0.00E+OO
- 1. 69E+04 O.OOE+OO
- 1. 84E+05
- 1. 43E+07 4.29E+05 23 Ag-110m 1.69E+04
- 1. 14E+04
- 9. 14E+03 O.OOE+OO
- 2. 12E+04 5.48E+06 1.00E+05 24 Sb-124
- 5. 74E+04
- 7. 40E+02 2.00E+04
- 1. 26E+02
- 0. OOE+OO 3.24E+06
- 1. 64E+05 25 Sb-125 9.84E+04 7.59E+02 2.07E+04
- 9. 10E+01 0.00E+OO 2.32E+06 4.03E+04 26 Sb-126 6.36E+03 9.69E+01
- 2. 28E+03
- 3. 70E+01 O.OOE+OO
- 1. 06E+06
- 2. 10E+05 27 Te-127m 2.49E+04
- 8. 55E+03 3.02E+03 6.07E+03 6.36E+04
- 1. 48E+06
- 7. 14E+04 28 Te-129m
- 1. 92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04
- 1. 76E+06
- 1. 82E+05 29 1-131 4.81E+04
- 4. 81E+04
- 2. 73E+04
- 1. 62E+07 7.88E+04 O.OOE+OO 2.84E+03 30 1-133
- 1. 66E+04
- 2. 03E+04
- 7. 70E+03
- 3. 85E+06 3.38E+04 O.OOE+OO 5.48E+03 31 Cs-134 6.51E+05
- 1. 01E+06
- 2. 25E+05
- 0. OOE+OO 3.30E+05 1.21E+05 3.85E+03 32 Cs-136 6.51E+04
- 1. 71 E+05
- 1. 16E+05 O.OOE+OO 9.55E+04
- 1. 45E+04
- 4. 18E+03 33 Cs-137 9.07E+05 8.25E+05
- 1. 28E+05 O.OOE+OO
- 2. 82E+05
- 1. 04E+05 3.62E+03 34 Ba-140 7.40E+04 6.48E+01 4.33E+03
- 0. OOE+OO
- 2. 11 E+01
- 1. 74E+06
- 1. 02E+05 35 La-140
- 6. 44E+02 2.25E+02
- 7. 55E+01 O.OOE+OO O.OOE+OO
- 1. 83E+05 2.26E+05 36 Ce-141 3.92E+04 1.95E+04
- 2. 90E+03 O.OOE+OO 8.55E+03 5.44E+05
- 5. 66E+04 37 Ce-144
- 6. 77E+06
- 2. 12E+06 3.61E+05 O.OOE+OO 1.17E+06
- 1. 20E+07 3.89E+05 cal cul at ed per CDCM equat i on 2. 2-13
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS ATTACHMENT I Page 1 of 1 Procedure Number:
l/2-0DC-2.02 Unit:
Level Of Use:
1/2 General Skill Reference Revision:
Page Number:
11 91 of 131 MODES OF GASEOUS RELEASE TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEA VER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CPR 20 AND 10 CPR 50 RELEASE RELEASE RELEASE RELEASE RELEASE POINT MODEi M0DE2 M0DE3 M0DE4 RP I; W-1, Auxiliary Aux. Bldg.
Containment Same As Mode 1 Same As Mode 1 Building Vent<1)
Ventilation Purge<3)
RP 2; CV-I, Rx Leakage Collection Same As Mode 1 Same As Mode 1 Same As Mode 1 Containment/SLCRS Vent(l)
Exhaust and Containment Purge<3)
RP 3; PV-1/2, Gaseous Main Cond. Air Same As Mode 1 Same As Mode 1 Same As Mode 1 Waste/Process Vent<2)
Ejector, Waste Gas, and Containment Containment Purge Vacuum RP 4; W-2 SLCRS Contiguous Areas Containment Same As Mode 1 Same As Mode 1 Unfiltered Pathway(l)
Purge<3)
RP 5; CV-2, SLCRS Filtered Aux. Bldg.
Same As Mode 1 Same As Mode 1 Same As Mode 1 Pathway(l)
Ventilation and Containment Purge<3)
RP 6; CB-2, Condensate (4)
(4)
(4)
(4)
Polishing Bldg Vent())
RP 7; WV-2, Waste Gas (4)
(4)
(4)
(4).
Storage Vault Vent(!)
RP 8;DV-2, (4)
(4)
(4)
(4)
Decontamination Bldg Vent(l)
RP 9; TV-2, Turbine Bldg (4)
(4)
(4)
(4)
Vent(!)
NOTE: For the purpose of implementing 10 CPR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.
(I) Continuous ground level meteorology is applicable (Z) Continuous elevated meteorology is applicable
<3) Mode established by purge from one unit, all other release points remain same as Mode 1 (4) Not normally a radioactive release point
I' Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 Q? of 131 ATTACHMENT J Page 1 of 19 P&I ORGAN DOSE FACTORS Table 2.3-2 R VALUES FCR BEAVER VALLEY SI TE
( nr em' yr per uCi / cu rret er)
Pathway = I nhal at i on Age G"oup = Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI - LLI 1 H-3 O.OOE+OO 1.26E+03
- 1. 26E+03
- 1. 26E+03
- 1. 26E+03
- 1. 26E+03
- 1. 26E+03 2
- 1. 82E+04 3.41E+03 3.41E+03
- 3. 41 E+03 3.41E+03
- 3. 41 E+03 3.41E+03 3
P-32
- 1. 32E+06
- 7. 71E+04 5.01E+04
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 8. 64E+04 4 Cr-51 O.OOE+OO O.OOE+OO
- 1. OOE+02
- 5. 95E+01
- 2. 28E+01
- 1. 44E+04 3.32E+03 5
M,- 54 O.OOE+OO
- 3. 96E+04 6.30E+03 O.OOE+OO
- 9. 84E+03
- 1. 40E+06
- 7. 74E+04 6
Fe-59
- 1. 18E+04
- 2. 78E+04
- 1. 06E+04 O.OOE+OO
- 0. OOE+OO
- 1. 02E+06
- 1. 88E+05 7
Co-57 O.OOE+OO 6.92E+02
- 6. 71E+02
- 0. OOE+OO
- 0. OOE+OO
- 3. 70E+05
- 3. 14E+04 8
Co-58
- 0. OOE+OO
- 1. 58E+03 2.07E+03 O.OOE+OO
- 0. OOE+OO
- 9. 28E+05
- 1. 06E+05 9 Co-60 O.OOE+OO
- 1. 15E+04
- 1. 48E+04 O.OOE+OO
- 0. OOE+OO
- 5. 97E+06
- 2. 85E+05 10 Zn-65
- 3. 24E+04.
- 1. 03E+05 4.66E+04
- 0. OOE+OO
- 6. 90E+04
- 8. 64E+05 5.34E+04 11 Se-75 O.OOE+OO
- 2. 97E+03
- 1. 10E+03 O.OOE+OO
- 3. 69E+03
- 4. 11 E+05
- 3. 54E+04 12 Rb-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 66E+04 13 Sr-89
- 3. 04E+05 O.OOE+OO
- 8. 72E+03 O.OOE+OO
- 0. OOE+OO
- 1. 40E+06
- 3. 50E+05 14 Sr-90 9.92E+07 O.OOE+OO
- 6. 10E+06 O.OOE+OO
- 0. OOE+OO
- 9. 60E+06
- 7. 22E+05 15 Y-91 4.62E+05 O.OOE+OO
- 1. 24E+04 O.OOE+OO O.OOE+OO
- 1. 70E+06 3.85E+05 16 Zr-95
- 1. 07E+05 3.44E+04 2.33E+04 O.OOE+OO
- 5. 42E+04
- 1. 77E+06
- 1. 50E+05 17 l\\!J-95
- 1. 41E+04 7.82E+03
- 4. 21E+03 O.OOE+OO
- 7. 74E+03
- 5. 05E+05
- 1. 04E+05 18 Nb-97
- 2. 22E'- 01
- 5. 62E- 02
- 2. 05E-02 O.OOE+OO
- 6. 54E-02 2.40E+03 2.42E+02 19 rvb-99 O.OOE+OO
- 1. 21 E+02 2.30E+01 O.OOE+OO 2.91E+02
- 9. 12E+04
- 2. 48E+05 20 Tc-99m
- 1. 03E- 03
- 2. 91.E- 03
- 3. ?OE- 02 O.OOE+OO
- 4. 42E-02
- 7. 64E+02
- 4. 16E+03 21 Ru-103 1.53E+03 O.OOE+OO 6.58E+02
- 0. OOE+OO
- 5. 83E+03
- 5. 05E+05
- 1. 10E+05 22 Ru-106
- 6. 91E+04 O.OOE+OO
- 8. 72E+03
- 0. OOE+OO
- 1. 34E+05
- 9. 36E+06
- 9. 12E+05 23 Ag-110m
- 1. 08E+04
- 1. OOE+04 5.94E+03 O.OOE+OO
- 1. 97E+04
- 4. 63E+06
- 3. 02E+05 24 Sb-124
- 3. 12E+04 5.89E+02
- 1. 24E+04
- 7. 55E+01
- 0. OOE+OO
- 2. 48E+06
- 4. 06E+05 25 Sb-125
- 5. 34E+04 5.95E+02
- 1. 26E+04 5.40E+01
- 0. OOE+OO
- 1. 74E+06
- 1. 01E+05 26 Sb-126 3.60E+03 7.30E+01
- 1. 30E+03
- 2. 20E+01
- 0. OOE+OO 7.66E+05 4.81E+05 27 Te-127m
- 1. 26E+04
- 5. 77E+03
- 1. 57E+03 3.29E+03
- 4. 58E+04 9.60E+05
- 1. 50E+05 28 Te-129m
- 9. 76E+03 4.67E+03
- 1. 58E+03
- 3. 44E+03
- 3. 66E+04
- 1. 16E+06
- 3. 83E+05 29 I -131 2.52E+04 3.58E+04 2.05E+04
- 1. 19E+07
- 6. 13E+04 0.00E+OO 6.28E+03 30 1-133 8.64E+03
- 1. 48E+04 4.52E+03
- 2. 15E+06
- 2. 58E+04
- 0. OOE+OO 8.88E+03 31 Cs-134
- 3. 73E+05 8.48E+05 7.28E+05 O.OOE+OO
- 2. 87E+05
- 9. 76E+04
- 1. 04E+04 32 Cs-136
- 3. 90E+04 1.46E+05
- 1. 10E+05 O.OOE+OO
- 8. 56E+04
- 1. 20E+04
- 1. 17E+04 33 Cs-137
- 4. 78E+05 6.21E+05 4.28E+05
- 0. OOE+OO
- 2. 22E+05
- 7. 52E+04
- 8. 40E+03 34 Ba-140 3.90E+04
- 4. 90E+01 2.57E+03 O.OOE+OO
- 1. 67E+01
- 1. 27E+06
- 2. 18E+05 35 La-140 3.44E+02
- 1. 74E+02 4.58E+01 O.OOE+OO O.OOE+OO
- 1. 36E+05 4.58E+05 36 Ce-141
- 1. 99E+04 1.35E+04
- 1. 53E+03
- 0. OOE+OO
- 6. 26E+03
- 3. 62E+05
- 1. 20E+05 37 Ce-144 3.43E+06
- 1. 43E+06
- 1. 84E+05 O,OOE+OO 8.48E+05
- 7. 78E+06
- 8. 16E+05 Cal cul at ed per CDCM equation 2. 3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 91 of 131 ATTACHMENTJ Page 2 of 19 P&I ORGAN DOSE FACTORS Table 2.3-3 R VALUES FCR BEAVER VALL'.EY SI TE
( rrr ent yr per ua / cu rret er)
Pathway= Inhalation Age G' oup = Teen Nuclide Bone Liver T.
Body Thyroid Kidney Lung G -LU 1 H-3
- 0. OOE+OO
- 1. 27E+03
- 1. 27E+03 1.27E+03
- 1. 27E+03
- 1. 27E+03
- 1. 27E+03 2
C.14
- 2. 60E+04
- 4. 87E+03
- 4. 87E+03 4.87E+03
- 4. 87E+03 4.87E+03 4.87E+03 3 P-32
- 1. 89E+06
- 1. 10E+05
- 7. 16E+04 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E+04 4
Cr-51
- 0. OOE+OO
- 0. OOE+OO
- 1. 35E+02
- 7. 50E+01 3.07E+01
- 2. 10E+04
- 3. OOE+03 5 M,-54
- 0. OOE+OO
- 5. 11 E+04
- 8. 40E+03 O.OOE+OO
- 1. 27E+04 1.98E+06 6.68E+04 6
Fe-59
- 1. 59E+04
- 3. 70E+04
- 1. 43E+04 O.OOE+OO
- 0. OOE+OO
- 1. 53E+06
- 1. 78E+05 7
- 0. OOE+OO
- 9. 44E+02 9.20E+02 O.OOE+OO O.OOE+OO 5.86E+05
- 3. 14E+04 8 Co-58
- 0. OOE+OO
- 2. 07E+03
- 2. 78E+03 O.OOE+OO O.OOE+OO
- 1. 34E+06
- 9. 52E+04 9
- 0. OOE+OO
- 1. 51E+04
- 1. 98E+04 O.OOE+OO
- 0. OOE+OO
- 8. 72E+06
- 2. 59E+05 10 Zn-65
- 3. 86E+04
- 1. 34E+05
- 6. 24E+04 O.OOE+OO 8.64E+04
- 1. 24E+06
- 4. 66E+04 11 Se-75
- 0. OOE+OO 4.20E+03
- 1. 57E+03 O.OOE+OO 5.27E+03
- 7. 10E+05
- 3. 55E+04 12 Rb-86 O.OOE+OO
- 1. 90E+05 8.40E+04 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 77E+04 13 Sr-89
- 4. 34E+05
- 0. OOE+OO
- 1. 25E+04 O.OOE+OO
- 0. OOE+OO 2.42E+06
- 3. 71E+05 14 Sr-90
- 1. 08E+08
- 0. OOE+OO 6.68E+06 O.OOE+OO
- 0. OOE+OO
- 1. 65E+07 7.65E+05 15 Y-91
- 6. 61E+05
- 0. OOE+OO
- 1. 77E+04 O.OOE+OO
- 0. OOE+OO
- 2. 94E+06
- 4. 09E+05 16 Zr-95
- 1. 46E+05 4.58E+04
- 3. 15E+04 O.OOE+OO
- 6. 74E+04 2.69E+06
- 1. 49E+05 17 NJ-95
- 1. 86E+04
- 1. 03E+04
- 5. 66E+03 O.OOE+OO
- 1. OOE+04
- 7. 51E+05 9.68E+04 18 N:>- 97
- 3. 14E- 01
- 7. 78E-02
- 2. 84E-02 O.OOE+OO
- 9. 12E- 02
- 3. 93E+03
- 2. 17E+03 19 M>-99 O.OOE+OO
- 1. 69E+02
- 3. 22E+01 O.OOE+OO
- 4. 11E+02
- 1. 54E+05
- 2. 69E+05 20 Tc-99m
- 1. 38E-03
- 3. 86E-03
- 4. 99E- 02 O.OOE+OO
- 5. 76E-02
- 1. 15E+03
- 6. 13E+03 21 Ru-103
- 2. 10E+03
- 0. OOE+OO
- 8. 96E+02 O.OOE+OO 7.43E+03
- 7. 83E+05
- 1. 09E+05 22 Ru-106
- 9. 84E+04
- 0. OOE+OO
- 1. 24E+04 0.00E+OO
- 1. 90E+05
- 1. 61E+07 9.60E+05 23 Ag-110m
- 1. 38E+04
- 1. 31E+04
- 7. 99E+03
- 0. OOE+OO
- 2. 50E+04
- 6. 75E+06
- 2. 73E+05 24 Sb-124
- 4. 30E+04
- 7. 94E+02
- 1. 68E+04
- 9. 76E+01
- 0. OOE+OO
- 3. 34E+06
- 3. 98E+05 25 Sb-125
- 7. 38E+04
- 8. 08E+02
- 1. 72E+04
- 7. 04E+01 O.OOE+OO
- 2. 74E+06
- 9. 92E+04 26 Sb-126
- 4. 95E+03
- 1. 02E+02
- 1. 78E+03
- 2. 80E+01
- 0. OOE+OO
- 1. 24E+06
- 4. 81E+05 27 Te-127m
- 1. 80E+04
- 8. 16E+03
- 2. 18E+03 4.38E+03
- 6. 54E+04
- 1. 66E+06
- 1. 59E+05 28 Te-129m
- 1. 39E+04
- 6. 58E+03
- 2. 25E+03 4.58E+03
- 5. 19E+04
- 1. 98E+06 4.05E+05 29 1-131
- 3. 54E+04
- 4. 91 E+04
- 2. 64E+04
- 1. 46E+07 8.40E+04
- 0. OOE+OO
- 6. 49E+03 30 1-133
- 1. 22E+04 2.05E+04
- 6. 22E+03 2.92E+06 3.59E+04
- 0. OOE+OO
- 1. 03E+04 31
- Cs-134
- 5. 02E+05
- 1. 13E+06
- 5. 49E+05
- 0. OOE+OO
- 3. 75E+05
- 1. 46E+05
- 9. 76E+03 32 Cs-136
- 5. 15E+04
- 1. 94E+05
- 1. 37E+05 O.OOE+OO
- 1. 10E+05
- 1. 78E+04
- 1. 09E+04 33 Cs~ 137
- 6. 70E+05
- 8. 48E+05
- 3. 11 E+05 O.OOE+OO
- 3. 04E+05
- 1. 21E+05 8.48E+03 34 Ba-140 5.47E+04
- 6. 70E+01
- 3. 52E+03 O.OOE+OO 2.28E+01
- 2. 03E+06
- 2. 29E+05 35 La-140
- 4. 79E+02
- 2. 36E+02
- 6. 26E+01
- 0. OOE+OO
- 0. OOE+OO
- 2. 14E+05
- 4. 87E+05 36 c.e-141
- 2. 84E+04
- 1. 90E+04
- 2. 17E+03
- 0. OOE+OO
- 8. 88E+03
- 6. 14E+05
- 1. 26E+05 37 c.e-144 4.89E+06
- 2. 02E+06
- 2. 62E+05 O.OOE+OO
- 1. 21E+06
- 1. 34E+07
- 8. 64E+05 Calculated per CDCM equat i on 2. 3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11
()4. of 131 ATTACHMENTJ Page 3 of 19 P&I ORGAN DOSE FACTORS Table 2. 3-4 R VALUES 'FCR BEAVER VALLEY SI TE (mentyr per ua / cu rret er)
Pathway = I nhal at i on Age G"oup = Chi Id Nuclide Bone Liver T.
Body Thyroid Kidney Lung G -LLI 1
H-3 O.OOE+OO
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03
- 1. 12E+03 2
Cr 14 3.59E+04
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03
- 6. 73E+03 3
P-32
- 2. 60E+06
- 1. 14E+05 9.88E+04 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 4. 22E+04 4
Cr-51 O.OOE+OO
- 0. OOE+OO
- 1. 54E+02
- 8. 55E+01
- 2. 43E+01
- 1. 70E+04
- 1. 08E+03 5 Ml-54 O.OOE+OO 4.29E+04 9.51E+03
- 0. OOE+OO 1.. 00E+04
- 1. 58E+06
- 2. 29E+04 6
Fe-59 2.07E+04
- 3. 34E+04
- 1. 67E+04 O.OOE+OO
- 0. OOE+OO
- 1. 27E+06
- 7. 07E+04 7
Co-57 O.OOE+OO 9.03E+02
- 1. 07E+03
- 0. OOE+OO O.OOE+OO
- 5. 07E+05
- 1. 32E+04 8
Co-58 O.OOE+OO
- 1. 77E+03
- 3. 16E+03
- 0. OOE+OO
- 0. OOE+OO
- 1. 11 E+06
- 3. 44E+04 9
Co-60 O.OOE+OO
- 1. 31 E+04
- 2. 26E+04 O.OOE+OO
- 0. OOE+OO
- 7. 07E+06
- 9. 62E+04 10 Zn-65 4.26E+04
- 1. 13E+05 7.03E+04
- 0. OOE+OO
- 7. 14E+04
- 9. 95E+05
- 1. 63E+04 11 Se-75 O.OOE+OO 4.40E+03
- 2. 17E+03 O.OOE+OO 5.11E+03
- 6. 33E+05
- 1. 69E+04 12 Rb-86 O.OOE+OO
- 1. 98E+05
- 1. 14E+05 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO 7.99E+03 13 Sr-89
- 5. 99E+05
- 0. OOE+OO *
- 1. 72E+04 O.OOE+OO 0.00E+OO
- 2. 16E+06
- 1. 67E+05 14 Sr-90
- 1. 01E+08 O.OOE+OO
- 6. 44E+06 O.OOE+OO
- 0. OOE+OO
- 1. 48E+07 3.43E+05 15 Y-91
- 9. 14E+05 O.OOE+OO
- 2. 44E+04
- 0. OOE+OO 0.00E+OO
- 2. 63E+06
- 1. 84E+05 16 Zr-95
- 1. 90E+05
- 4. 18E+04
- 3. 70E+04
- 0. OOE+OO 5.96E+04
- 2. 23E+06
- 6. 11E+04 17 Nb-95
- 2. 35E+04
- 9. 18E+03 6.55E+03 O.OOE+OO
- 8. 62E+03
- 6. 14E+05
- 3. 70E+04 18 NJ-97
- 4. 29E- 01
- 7. 70E- 02
- 3. 60E- 02 O.OOE+OO
- 8. SSE- 02
- 3. 42E+03
- 2. 78E+04 19 M)-99 O.OOE+OO
- 1. 72E+02
- 4. 26E+01 O.OOE+OO
- 3. 92E+02
- 1. 35E+05
- 1. 27E+05 20 Tc-99m
- 1. 78E- 03
- 3. 48E-03
- 5. 77E-02
- 0. OOE+OO
- 5. 07E- 02 9.51E+02 4.81E+03 21 Ru-103
- 2. 79E+03 O.OOE+OO
- 1. 07E+03 O.OOE+OO
- 7. 03E+03
- 6. 62E+05 4.48E+04 22 Ru-106
- 1. 36E+05 O.OOE+OO
- 1. 69E+04 O.OOE+OO
- 1. 84E+05
- 1. 43E+07
- 4. 29E+05 23 Ag-110m
- 1. 69E+04
- 1. 14E+04
- 9. 14E+03 O.OOE+OO
- 2. 12E+04
- 5. 48E+06
- 1. OOE+OS 24 Sb-124
- 5. 74E+04 7.40E+02 2.00E+04
- 1. 26E+02
- 0. OOE+OO
- 3. 24E+06
- 1. 64E+05 25 Sb-125 9.84E+04 7.59E+02
- 2. 07E+04
- 9. 10E+01
- 0. OOE+OO
- 2. 32E+06
- 4. 03E+04 26 Sb-126 6.36E+03 9.69E+01 2.28E+03
- 3. 70E+01
- 0. OOE+OO
- 1. 06E+06
- 2. 10E+05 27 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04
- 1. 48E+06
- 7. 14E+04 28 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03
- 5. 03E+04
- 1. 76E+06
- 1. 82E+05 29 I -131 4.81E+04 4.81E+04
- 2. 73E+04
- 1. 62E+07 7.88E+04
- 0. OOE+OO
- 2. 84E+03 30 1-133
- 1. 66E+04 2.03E+04
- 7. 70E+03
- 3. 85E+06
- 3. 38E+04
- 0. OOE+OO
- 5. 48E+03 31 Cs-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+OO 3.30E+05
- 1. 21 E+OS
- 3. 85E+03 32 Cs-136 6.51E+04
- 1. 71E+05
- 1. 16E+05
- 0. OOE+OO
- 9. 55E+04
- 1. 45E+04
- 4. 18E+03 33 Cs-137 9.07E+05 8.25E+05
- 1. 28E+05 O.OOE+OO
- 2. 82E+05
- 1. 04E+05
- 3. 62E+03 34 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO
- 2. 11 E+01
- 1. 74E+06
- 1. 02E+05 35 La-140 6.44E+02 2.25E+02 7.55E+01 O.OOE+OO
- 0. OOE+OO
- 1. 83E+05
- 2. 26E+05 36 Ce-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+OO
- 8. 55E+03
- 5. 44E+05
- 5. 66E+04 37 Ce-144
- 6. 77E+06
- 2. 12E+06 3.61E+05 O.OOE+OO
- 1. 17E+06
- 1. 20E+07
- 3. 89E+05 Cal cul at ed per ax:Mequation 2. 3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 Q" of 131 ATTACHMENT J Page 4 of 19 P&I ORGAN DOSE FACTORS Table 2. 3-5 R VALLES Fffi BEAVER VALLEY SI TE
( nTent yr per ua / cu rret er)
Pathway= lnhalati on Age G" oup = I nf ant Nuclide Bone Liver T. Body Thyroid Kidney Lung G -LLI 1 H-3 O.OOE+OO 6.47E+02 6.47E+02
- 6. 47E+02 6.47E+02 6.47E+02
- 6. 47E+02 2 C-14 2.65E+04 5.31E+03
- 5. 3.1E+03
- 5. 31 E+03
- 5. 31 E+03 5.31E+03 5.31E+03 3 P-32 2.03E+06
- 1. 12E+05
- 7. 74E+04 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 61 E+04 4 Cr-51 0.00E+OO O.OOE+OO
- 8. 95E+01
- 5. 75E+01
- 1. 32E+01
- 1. 28E+04
- 3. 57E+02 5 Ml-54 O.OOE+OO
- 2. 53E+04 4.98E+03
- 0. OOE+OO
- 4. 98E+03
- 1. OOE+06
- 7. 06E+03 6 Fe-59
- 1. 36E+04
- 2. 35E+04 9.48E+03 O.OOE+OO O.OOE+OO
- 1. 02E+06
- 2. 48E+04 7 Co-57 O.OOE+OO 6.51E+02 6.41E+02 O.OOE+OO
- 0. OOE+OO
- 3. 79E+05
- 4. 86E+03 8 Co-58 O.OOE+OO
- 1. 22E+03 1.82E+03
- 0. OOE+OO
- 0. OOE+OO
- 7. 77E+05
- 1. 11 E+04 9 Co-60 O.OOE+OO
- 8. 02E+03
- 1. 18E+04 O.OOE+OO
- 0. OOE+OO 4.51E+06
- 3. 19E+04 10 Zn-65
- 1. 93E+04
- 6. 26E+04
- 3. 11E+04 O.OOE+OO 3.25E+04 6.47E+05
- 5. 14E+04 11 Se-75
- 0. OOE+OO
- 3. 54E+03 1.48E+03 O.OOE+OO 3.08E+03 5.56E+05
- 6. 37E+03 12 Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 3. 04E+03 13 Sr-89 3.98E+05 O.OOE+OO
- 1. 14E+04
- 0. OOE+OO O.OOE+OO
- 2. 03E+06 6.40E+04 14 Sr-90
- 4. 09E+07
- 0. OOE+OO 2.59E+06
- 0. OOE+OO O.OOE+OO
- 1. 12E+07
- 1. 31E+05 15 Y-91
- 5. 88E+05 O.OOE+OO 1.57E+04 O.OOE+OO
- 0. OOE+OO 2.45E+06
- 7. 03E+04 16 Zr-95
- 1. 15E+05
- 2. 79E+04
- 2. 03E+04
- 0. OOE+OO
- 3. 11E+04
- 1. 75E+06
- 2. 17E+04 17 N>-95
- 1. 57E+04 6.43E+03
- 3. 78E+03 O.OOE+OO
- 4. 72E+03
- 4. 79E+05
- 1. 27E+04 18 N>-97
- 3. 42E- 01
- 7. 29E- 02
- 2. 63E-02 0.00E+OO
- 5. 70E- 02
- 3. 32E+03
- 2. 69E+04 19 l\\.lb-99 O.OOE+OO
- 1. 65E+02 3.23E+01
- 0. OOE+OO
- 2. 65E+02
- 1. 35E+05
- 4. 87E+04 20 Tc-99m
- 1. 40E- 03
- 2. 88E- 03
- 3. 72E- 02
- 0. OOE+OO
- 3. 11E-02
- 8. 11E+02
- 2. 03E+03 21 Ru-103 2.02E+03 O.OOE+OO
- 6. 79E+02 O.OOE+OO
- 4. 24E+03
- 5. 52E+05 1.61E+04 22 Ru-106 8.68E+04 O.OOE+OO
- 1. 09E+04 O.OOE+OO
- 1. 07E+05
- 1. 16E+07
- 1. 64E+05 23 Ag-110m 9.98E+03 7.22E+03
- 5. OOE+03
- 0. OOE+OO
- 1. 09E+04 3.67E+06
- 3. 30E+04 24 Sb-124
- 3. 79E+04 5.56E+02 1.20E+04
- 1. 01E+02 O.OOE+OO
- 2. 65E+06 5.91E+04 25 Sb-125
- 5. 17E+04
- 4. 77E+02
- 1. 09E+04
- 6. 23E+01 O.OOE+OO
- 1. 64E+06
- 1. 47E+04 26 Sb-126
- 4. 31E+03 8.41E+01
- 1. 55E+03
- 3. 29E+01 O.OOE+OO 9.63E+05
- 7. 46E+04 27 Te-127m 1.67E+04 6.90E+03 2.07E+03
- 4. 87E+03
- 3. 75E+04
- 1. 31E+06
- 2. 73E+04 28 Te-129m
- 1. 41E+04 6.09E+03 2.23E+03
- 4. 21 E+03
- 3. 18E+b4
- 1. 68E+06
- 6. 90E+04 29 I - 131
- 3. 79E+04 4.44E+04
- 1. 96E+04
- 1. 48E+07
- 5. 18E+04 O.OOE+OO
- 1. 06E+03 30 1-133
- 1. 32E+04
- 1. 92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO
- 2. 16E+03 31 Cs-134 3.96E+05 7.03E+05
- 7. 45E+04 O.OOE+OO
- 1. 90E+05 7.97E+04
- 1. 33E+03 32 Cs-136
- 4. 83E+04 1.35E+05 5.29E+04 O.OOE+OO
- 5. 64E+04
- 1. 18E+04
- 1. 43E+03 33 Cs-137 5.49E+05
- 6. 12E+05 4.55E+04
- 0. OOE+OO
- 1. 72E+05
- 7. 13E+04
- 1. 33E+03 34 Ba-140
- 5. 60E+04 5.60E+01 2.90E+03
- 0. OOE+OO
- 1. 34E+01
- 1. 60E+06
- 3. 84E+04 35 La-140 5.05E+02 2.00E+02
- 5. 15E+01
- 0. OOE+OO
- 0. OOE+OO
- 1. 68E+05 8.48E+04 36 Ce-141
- 2. 77E+04
- 1. 67E+04
- 1. 99E+03
- 0. OOE+OO
- 5. 25E+03
- 5. 17E+05
- 2. 16E+04 37 Ce-144
- 3. 19E+06
- 1. 21E+06
- 1. 76E+05
- 0. OOE+OO
- 5. 38E+05 9.84E+06
- 1. 48E+05 Calculated per CDCM equation 2. 3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11
%of Bl ATTACHMENTJ Page 5 of 19 P&I ORGAN DOSE FACTORS Table 2. 3-6 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er - rrr err/ yr per uCi I sec)
Pathway = G'ound Nuclide Bone Liver T.
Body Thyroid Kidney Lung G -LLI 1
H, 3 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 2
C-14 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 3
P-32 O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 4
Cr-51 4.66E+06 4.66E+06
- 4. 66E+06
- 4. 66E+06
- 4. 66E+06
- 4. 66E+06
- 4. 66E+06 5 Ml-54
- 1. 39E+09
- 1. 39E+09
- 1. 39E+09
- 1. 39E+09
- 1. 39E+09
- 1. 39E+09
- 1. 39E+09 6
Fe-59
- 2. 73E+08
- 2. 73E+08
- 2. 73E+08
- 2. 73E+08
- 2. 73E+08
- 2. 73E+08
- 2. 73E+08 7
Co-57 O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 8
Co-58
- 3. 79E+08
- 3. 79E+08
- 3. 79E+08
- 3. 79E+08
- 3. 79E+08
- 3. 79E+08
- 3. 79E+08 9
- 2. 15E+10
- 2. 15E+10
- 2. 15E+10
- 2. 15E+10
- 2. 15E+10
- 2. 15E+10
- 2. 15E+10 10 Zn-65 7.47E+08 7.47E+08 7.47E+08 7.47E+08
- 7. 47E+08 7.47E+08 7.47E+08 11 Se-75
- 4. 06E+08 4.06E+08 4.06E+08
- 4. 06E+08
- 4. 06E+08
- 4. 06E+08
- 4. 06E+08 12 Rb-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06
- 8. 99E+06
- 8. 99E+06 8.99E+06 13 Sr-89
- 2. 16E+04
- 2. 16E+04
- 2. 16E+04
- 2. 16E+04
- 2. 16E+04
- 2. 16E+04
- 2. 16E+04 14 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 15 Y-91
- 1. 07E+06
- 1. 07E+06
- 1. 07E+06
- 1. 07E+06
- 1. 07E+06
- 1. 07E+06
- 1. 07E+06 16 Zr-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08
- 2. 45E+08
- 2. 45E+08 17 JIJb-95
- 1. 37E+08
- 1. 37E+08 1.37E+08
- 1. 37E+08
- 1. 37E+08
- 1. 37E+08
- 1. 37E+08 18 N:>- 97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 19 Wb-99 4.00E+06 4.00E+06 4.00E+06
- 4. OOE+06
- 4. OOE+06
- 4. OOE+06
- 4. OOE+06 20 Tc-99m
- 1. 84E+05
- 1. 84E+05
- 1. 84E+05
- 1. 84E+05
- 1. 84E+05
- 1. 84E+05
- 1. 84E+05 21 Ru-103
- 1. 08E+08
- 1. 08E+08
- 1. 08E+08
- 1. 08E+08
- 1. 08E+08
- 1. 08E+08
- 1. 08E+08 22 Ru-106 4.22E+08 4.22E+08 4.22E+08
- 4. 22E+08
- 4. 22E+08
- 4. 22E+08
- 4. 22E+08 23 Ag-110m 3.44E+09 3.44E+09 3.44E+09 3.44E+09
- 3. 44E+09
- 3. 44E+09
- 3. 44E+09 24 Sb-124 O.OOE+OO O.OOE+OO
, 0. OOE+OO
- 0. OOE+OO -
- 0. OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125
- 0. OOE+OO O.OOE+OO 0.00E+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m
- 9. 17E+04
- 9. 17E+04
- 9. 17E+04
- 9. 17E+04
- 9. 17E+04
- 9. 17E+04
- 9. 17E+04 28 Te-129m
- 1. 98E+07
- 1. 98E+07
- 1. 98E+07
- 1. 98E+07
- 1. 98E+07
- 1. 98E+07
- 1. 98E+07 29 I -131
- 1. 72E+07
- 1. 72E+07
- 1. 72E+07
- 1. 72E+07
- 1. 72E+07
- 1. 72E+07
- 1. 72E+07 30 1-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06
- 2. 45E+06
- 2. 45E+06 2.45E+06 31 Cs-134 6.86E+09 6.86E+09 6.86E+09
- 6. 86E+09
- 6. 86E+09 6.86E+09 6.86E+09 32 Cs-136
- 1. 51E+08 1.51E+08
- 1. 51E+08
- 1. 51E+08
- 1. 51E+08
- 1. 51 E+08
- 1. 51E+08 33 Cs-137 1.03E+10 1.03E+10
- 1. 03E+10
- 1. 03E+10 1.03E+10 1.03E+10
- 1. 03E+10 34 Ba-140 2.05E+07 2.05E+07 2.05E+07
- 2. 05E+07
- 2. 05E+07
- 2. 05E+07
- 2. 05E+07 35 La-140 1.92E+07
- 1. 92E+07
- 1. 92E+07
- 1. 92E+07
- 1. 92E+07
- 1. 92E+07
- 1. 92E+07 36 Ce-141
- 1. 37E+07
- 1. 37E+07
- 1. 37E+07
- 1. 37E+07
- 1. 37E+07
- 1. 37E+07
- 1. 37E+07 37 Ce-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07
- 6. 96E+07 6.96E+07
- 6. 96E+07 Gal cul at ed per CDCMequation 2. 3-23
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pathway= Vegetation Age G" oup = Adul t Nuclide 1
H-3 2
C.14 3
P-32 4
Cr-51 5 Ml-54 6
Fe-59 7
Co-57 8
Co-58 9
Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr~ 90 15 Y-91 15 Zr-95 17 N,- 95 18 N,-97 19 11/b-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 1-133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone O.OOE+OO
- 8. 97E+05
- 1. 40E+09
- 0. OOE+OO
- 0. OOE+OO
- 1. 26E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 3. 17E+08
- 0. OOE+OO
- 0. OOE+OO
- 9. 97E+09
- 6. 05E+11
- 5. 11 E+06
- 1. 17E+06
- 1. 42E+05
- 2. 16E- 06 O.OOE+OO
- 3. 10E+OO
- 4. 77E+06
- 1. 93E+08
- 1. 05E+07 1.04E+08
- 1. 37E+08 7.01E+06 3.49E+08 2.51E+08 8.08E+07
- 2. 09E+06 4.67E+09 4.27E+07 6.36E+09 1.29E+08
- 1. 98E+03
- 1. 97E+05 3.29E+07 ATTACHMENT J Page 6 of 19 P&I ORGAN DOSE FACTORS Table 2.3-7 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-nrentyr per ua/sec)
Liver 2.26E+03
- 1. 79E+05
- 8. 74E+07 O.OOE+OO
- 3. 13E+08
- 2. 96E+08
- 1. 17E+07 3.07E+07
- 1. 67E+08 1.01E+09 2.65E+08
- 2. 19E+08 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 3. 77E+05 7.92E+04
- 5. 46E- 07
- 6. 15E+06
- 8. 77E+OO O.OOE+OO
- 0. OOE+OO
- 9. 75E+06
- 1. 96E+06
- 1. 53E+06
- 1. 43E+05
- 1. 25E+08
- 9. 38E+07
- 1. 16E+08-
- 3. 63E+06
- 1. 11E+10
- 1. 69E+08
- 8. 70E+09
- 1. 61.E+05
- 9. 97E+02
- 1. 33E+05
- 1. 38E+07 T.
Body
- 2. 26E+03
- 1. 79E+05 5.43E+07
- 4. 64E+04 5.97E+07
- 1. 14E+08
- 1. 95E+07
- 6. 89E+07 3.69E+08 4.56E+OB
- 1. 03E+08
- 1. 02E+08
- 2. 86E+08 -
- 1. 48E+11 1.37E+05 2.55E+05 4.26E+04
- 1. 99E-07
- 1. 17E+06
- 1. 12E+02 2.06E+06 2.44E+07
- 5. 79E+06 4.11E+07
- 3. 25E+07 2.53E+06 4.26E+07 3.98E+07 6.62E+07
- 1. 11E+06 9.08E+09
- 1. 21E+08
- 5. 70E+09 8.42E+06 2.63E+02
- 1. 51E+04
- 1. 77E+06 Thyroid 2.26E+03
. 1. 79E+05 O.OOE+OO
- 2. 78E+04 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
\\
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 2. 51E+05
- 1. 39E+05
- 4. 29E+04 8.92E+07
- 8. 64E+07
- 3. 79E+10
- 5. 33E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO Procedure Number:
Unit:
1/2 Revision:
I 1 Kidney 2.26E+03
- 1. 79E+05
- 0. OOE+OO
- 1. 02E+04 9.31E+07 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 6. 75E+08
- 3. 85E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 5. 91E+05
- 7. 83E+04
- 6. 37E- 07
- 1. 39E+07
- 1. 33E+02
- 1. 82E+07
- 3. 72E+08
- 1. 92E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 42E+09
- 1. 05E+09
- 1. 98E+08 6.33E+06
- 3. 59E+09
- 9. 38E+07
- 2. 95E+09 5.49E+04
- 0. OOE+OO
- 6. 19E+04
- 8. 16E+06 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
97 of 111 Lung 2.26E+03
- 1. 79E+05
- 0. OOE+OO
- 6. 16E+04
- 0. OOE+OO 8.28E+07 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 4. 30E+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 8.07E+07
- 1. 05E+08
- 4. 30E+06 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 1. 19E+09
- 1. 29E+07 9.81E+08
- 9. 24E+04 O.OOE+OO O.OOE+OO
- 0. OOE+OO GI - LLI
- 2. 26E+03
- 1. 79E+05
- 1. 58E+08
- 1. 17E+07
- 9. 59E+08
- 9. 88E+08
- 2. 97E+08
- 6. 23E+08
- 3. 14E+09
- 6. 36E+08 3.83E+07 4.33E+07
- 1. 60E+09 1.75E+10
- 2. 81 E+09
- 1. 19E+09
- 4. 81 E+08
- 2. 02E- 03
- 1. 43E+07
- 5. 19E+03
- 5. 57E+08
- 1. 25E+10 3.98E+09
- 2. 94E+09
- 1. 50E+09
- 5. 73E+08
- 1. 17E+09 1.27E+09
- 3. 05E+07
- 3. 26E+06
- 1. 94E+08
- 1. 91E+07
- 1. 68E+08
- 2. 65E+08
- 7. 32E+07
- 5. 10E+08
- 1. 11E+10 Al I nucl i des ( except H-3 and C. 14) cal cul at ed per CDCM equat i on 2. 3-26 H-3 cal cul at ed per CDCM equat i on 2. 3-29 C. 14 cal cul at ed per ERS-LIVR- 001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 98 of 131 ATTACHMENTJ Page 7 of 19 P&I ORGAN DOSE FACTORS Table 2.3-8 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er - rrr errl yr per uCi I sec)
Pathway: Vegetation Age Q-oup = Teen Nuclide Bone Liver T.
Body Thyroid Ki dney Lung GI - LLI 1
H-3 O.OOE+OO 2.59E+03
- 2. 59E+03
- 2. 59E+03 2.59E+03 2.59E+03 2.59E+03 2
- 1. 45E+06
- 2. 91 E+05 2.91E+05 2.91E+05 2.91E+05
- 2. 91E+05
- 2. 91E+05 3
P-32
- 1. 61 E+09
- 9. 98E+07
- 6. 24E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 35E+08 4
Cr-51
- 0. OOE+OO 0.00E+OO
- 6. 17E+04
- 3. 43E+04 1.35E+04 8.81E+04
- 1. 04E+07 5 Ml-54
- 0. OOE+OO
- 4. 54E+08
- 9. 01 E+07
- 0. OOE+OO
- 1. 36E+08
- 0. OOE+OO
- 9. 32E+08 6
Fe-59
- 1. 79E+08
- 4. 19E+08
- 1. 62E+08
- 0. OOE+OO 0.00E+OO
- 1. 32E+08
- 9. 90E+08 7
Co-57 O.OOE+OO
- 1. 79E+07 3.00E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 3. 33E+08 8
Co-58 O.OOE+OO 4.36E+07
- 1. OOE+08
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 6. 01E+08 9
- 0. OOE+OO 2.49E+08
- 5. 60E+08 O.OOE+OO 0.00E+OO O.OOE+OO 3.24E+09 10 Zn-65
- 4. 24E+08
- 1. 47E+09
- 6. 87E+08
- 0. OOE+OO
- 9. 42E+08
- 0. OOE+OO
- 6. 23E+08 16 Se-75
- 0. OOE+OO
- 4. 16E+08
- 1. 63E+08
- 0. OOE+OO
- 6. 12E+08
- 0. OOE+OO 4.25E+07 11. Rb-86
- 0. ciOE+OO
- 2. 74E+08
- 1. 29E+08 O; OOE+OO
- 0. OOE+OO O.OOE+OO 4.05E+07 12 Sr-89 1.51E+10
- 0. OOE+OO 4.34E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 80E+09 13 Sr-90 7.51E+11
- 0. OOE+OO
- 1. 85E+11
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 2.11E+10 14 Y-91
- 7. 84E+06
- 0. OOE+OO
- 2. 10E+05
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 3. 21 E+09 15 Zr-95
- 1. 72E+06
- 5. 43E+05
- 3. 74E+05
- 0. OOE+OO 7.98E+05
- 0. OOE+OO
- 1. 25E+09 17 Nb-95
- 1. 92E+05
- 1. 07E+05
- 5. 87E+04
- 0. OOE+OO
- 1. 03E+05 O.OOE+OO
- 4. 56E+08 18 Nb-97
- 2. DOE- 06
- 4. 97E- 07 1.81E-07
- 0. OOE+OO
- 5. 81 E- 07
- 0. OOE+OO
- 1. 19E-02 19 l'vb-99 O.OOE+OO 5.65E+06
- 1. 08E+06
- 0. OOE+OO
- 1. 29E+07
- 0. OOE+OO 1.01E+07 20 Tc-99m
- 2. 74E+OO
- 7. 64E+OO
- 9. 90E+01
- 0. OOE+OO
- 1. 14E+02 4.24E+OO
- 5. 02E+03 21 Ru-103
- 6. 82E+06
- 0. OOE+OO
- 2. 92E+06
- 0. OOE+OO 2.41E+07 O.OOE+OO
- 5. 70E+08 22 Ru-106
- 2. 38E+08 0.00E+OO
- 3. 90E+07
- 0. OOE+OO
- 5. 97E+08 O.OOE+OO 1.48E+10 23 Ag-11 Om
- 1. 52E+07
- 1. 43E+07
- 8. 72E+06
- 0. OOE+OO
- 2. 74E+07
- 0. OOE+OO
- 4. 03E+09 24 Sb-124
- 1. 54E+08
- 2. 84E+06 6.02E+07
- 3. 50E+05
- 0. OOE+OO
- 1. 35E+08
- 3. 11 E+09 25 Sb-125
- 2. 14E+08
- 2. 34E+06
- 5. 01E+07
- 2. 05E+05 O.OOE+OO
- 1. 88E+08
- 1. 67E+09 26 Sb-126 7.37E+06
- 1. 51E+05
- 2. 65E+06
- 4. 17E+04
- 0. OOE+OO 5.28E+06
- 4. 36E+08 27 Te-127m
- 5. 52E+08
- 1. 96E+08
- 6. 56E+07
- 1. 31E+08
- 2. 24E+09 O.OOE+OO
- 1. 37E+09 28 Te-129m
- 3. 62E+08
- 1. 34E+08
- 5. 73E+07
- 1. 17E+08
- 1. 51E+09 O.OOE+OO
- 1. 36E+09 29 I - 131 7.69E+07
- 1. 08E+08
- 5. 78E+07
- 3. 14E+10
- 1. 85E+08
- 0. OOE+OO
- 2. 13E+07 30 1-133
- 1. 94E+06
- 3. 29E+06
- 1. OOE+06
- 4. 59E+08
- 5. 77E+06
- 0. OOE+OO
- 2. 49E+06 31 Cs-134
- 7. 10E+09 1.67E+10
- 7. 75E+09
- 0. OOE+OO
- 5. 31 E+09
- 2. 03E+09
- 2. 08E+08 32 Cs-136
- 4. 38E+07
- 1. 72E+08
- 1. 16E+08
- 0. OOE+OO
- 9. 37E+07
- 1. 48E+07
- 1. 39E+07 33 Cs-137
- 1. 01E+10 1.35E+10 4.69E+09
- 0. OOE+OO
- 4. 59E+09
- 1. 78E+09
- 1. 92E+08 34 Ba-140
- 1. 38E+08
- 1. 69E+05
- 8. 90E+06
- 0. OOE+OO
- 5. 74E+04
- 1. 14E+05
- 2. 13E+08 35 La-140 1.81E+03
- 8. 88E+02 2.36E+02
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 5. 1 OE+07 36 Ce-141
- 2. 83E+05
- 1. 89E+05
- 2. 17E+04
- 0. OOE+OO
- 8. 90E+04
- 0. OOE+OO
- 5. 41 E+08 37 Ce-144
- 5. 27E+07
- 2. 18E+07
- 2. 83E+06
- 0. OOE+OO
- 1. 30E+07
- 0. OOE+OO
- 1. 33E+10 Al I nucl i des ( except H-3 and C-14) cal cul at ed H-3 cal cul at ed per CDCM equat i on* 2. 3-29 per CDa\\11 equat i on 2. 3-26 C-14 cal cul at ed per ERS-Uv'R- 001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 gg of 111 ATTACHMENTJ Page 8 of 19 P&I ORGAN DOSE FACTORS Table 2.3-9 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er - rrr errf yr per ua / sec)
Path11Vay = Vegetation Age Qoup = Chi Id Nuclide Bone Liver T.
Body Thyroid Kidney Lung GI - LLI 1 H-3 O.OOE+OO
- 4. 01 E+03
- 4. 01 E+03 4.01E+03 4.01E+03
- 4. 01 E+03 4.01E+03 2
- 3. 50E+06 7.01E+05 7.01E+05 7.01E+05 7.01E+05
- 7. 01E+05 7.01E+05 3 P-32 3.37E+09
- 1. 58E+08
- 1. 30E+08 O.OOE+OO
- 0. OOE+OO O.OOE+OO 9.32E+07 4
Cr-51 O.OOE+OO
- 0. OOE+OO
- 1. 17E+05 6.50E+04
- 1. 78E+04
- 1. 19E+05
- 6. 21 E+06 5
M,-54
- 0. OOE+OO
- 6. 65E+08
- 1. 77E+08 O.OOE+OO
- 1. 86E+08 O.OOE+OO
- 5. 58E+08 6
Fe-59
- 3. 98E+08 6.43E+08
- 3. 20E+08 O.OOE+OO O.OOE+OO
- 1. 87E+08
- 6. 70E+08 7
Co-57 O.OOE+OO
- 2. 99E+07
- 6. 04E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 2.45E+08 8
Co-58
- 0. OOE+OO
- 6. 44E+07
- 1. 97E+08 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 3. 76E+08 9
Co-60 O.OOE+OO
- 3. 78E+08
- 1. 12E+09 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 2. 1 OE+09 10 Zn-65
- 8. 13E+08
- 2. 17E+09
- 1. 35E+09 0.00E+OO
- 1. 36E+09
- 0. OOE+OO 3.80E+08 16 Se-75
- 0. OOE+OO 7.58E+08
- 3. 92E+08 O.OOE+OO L 03E+09 O.OOE+OO 3.51E+07 11 Rb-86
- 0. OOE+OO
- 4. 52E+08
- 2. 78E+08 O.OOE+OO 0.00E+OO
- 0. OOE+OO 2.91E+07 12 Sr-89
- 3. 60E+10 O.OOE+OO
- 1. 03E+09 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 39E+09 13 Sr-90 1.24E+12
- 0. OOE+OO
- 3. 15E+11
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 67E+10 14 Y-91
- 1. 86E+07
- 0. OOE+OO 4.99E+05 0.00E+OO 0.00E+OO O.OOE+OO 2.48E+09 15 Zr-95
- 3. 86E+06 8.48E+05 7.55E+05 O.OOE+OO
- 1. 21 E+06 O.OOE+OO 8.85E+08 17 Nb-95
- 4. 11 E+05
- 1. 60E+05
- 1. 14E+05 O.OOE+OO
- 1. 50E+05 O.OOE+OO
- 2. 96E+08 18 Nb-97
- 3. 65E-06
- 6. 59E-07
- 3. 08E- 07 O.OOE+OO
- 7. 31E-07
- 0. OOE+OO
- 2. 03E- 01 19 fvb-99
- 0. OOE+OO
- 7. 71E+06 1.91E+06 O.OOE+OO
- 1. 65E+07 O.OOE+OO 6.38E+06 20 Tc-99m
- 4. 71E+OO
- 9. 24E+OO
- 1. 53E+02 O.OOE+OO
- 1. 34E+02 4.69E+OO 5.26E+03 21 Ru-103
- 1. 53E+07
- 0. OOE+OO 5.90E+06 0.00E+OO
- 3. 86E+07 O.OOE+OO
- 3. 97E+08 22 Ru-106
- 7. 45E+08
- 0. OOE+OO 9.30E+07 O.OOE+OO
- 1. 01 E+09 O.OOE+OO
- 1. 16E+10 23 Ag-110m 3.21E+07
- 2. 17E+07
- 1. 73E+07 O.OOE+OO
- 4. 04E+07 O.OOE+OO
- 2. 58E+09 24 Sb-124
- 3. 52E+08
- 4. 57E+06
- 1. 23E+08
- 7. 77E+05
- 0. OOE+OO 1.95E+08 2.20E+09 25 Sb-125
- 4. 99E+08 3.85E+06
- 1. 05E+08 4.63E+05
- 0. OOE+OO
- 2. 78E+08
- 1. 19E+09 26 Sb-126
- 1. 39E+07
- 2. 12E+05
- 4. 98E+06
- 8. 13E+04
- 0. OOE+OO
- 6. 62E+06 2.80E+08 27 Te-127m
- 1. 32E+09
- 3. 56E+08
- 1. 57E+08
- 3. 16E+08
- 3. 77E+09 O.OOE+OO
- 1. 07E+09 28 Te-129m 8.41E+08 2.35E+08 1.31E+08
- 2. 71E+08 2.47E+09 O.OOE+OO
- 1. 03E+09 29 I - 131
- 1. 43E+08
- 1. 44E+08
- 8. 17E+07
- 4. 76E+10 2.36E+08 O.OOE+OO
- 1. 28E+07 30 I -133
- 3. 53E+06 4.37E+06
- 1. 65E+06
- 8. 12E+08
- 7. 28E+06 O.OOE+OO
- 1. 76E+06 31 Cs-134 1.60E+10 2.63E+10
- 5. 55E+09 O.OOE+OO
- 8. 15E+09 2.93E+09
- 1. 42E+08 32 Cs-136
- 8. 24E+07 2.27E+08
- 1. 47E+08 O.OOE+OO 1.21E+08
- 1. 80E+07
- 7. 96E+06 33 Cs-137
- 2. 39E+10 2.29E+10
- 3. 38E+09
- 0. OOE+OO
- 7. 46E+09 2.68E+09
- 1. 43E+08 34 Ba-140
- 2. 77E+08
- 2. 42E+07
- 1. 62E+07 O.OOE+OO
- 7. 89E+04
- 1. 45E+05
- 1. 40E+08 35 La-140 3.25E+03
- 1. 13E+03
- 3. 83E+02 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 3. 16E+07 36 Ce-141 6.56E+05 3.27E+05
- 4. 86E+05 O.OOE+OO
- 1. 43E+05 O.OOE+OO
- 4. 08E+08 37 Ce-144
- 1. 27E+08 3.98E+07
- 6. 78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 Al I nucl i des ( except H-3 and C-14) calculated per aJCM equat i on 2. 3-26 H-3 cal cul at ed per <DCM equat i on 2.3-29 C- \\4 cal cul at ed per ERS-LlvR-001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 100 of 131 ATTACHMENTJ Page 9 of19 P&I ORGAN DOSE FACTORS Table 2. 3-10 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er-rrr em yr per uCi / sec)
Pathway = ~at Age Q-oup = Adult Nuclide Bone Liver T. Body Thyr oi d Kidney Lung GI - LLI 1 1-1-3
- 0. OOE+OO 3.25E+02 3.25E+02 3.25E+02
- 3. 25E+02
- 3. 25E+02 3.25E+02 2 C-14
- 3. 33E+05
- 6. 66E+04 6.66E+04 6.66E+04
- 6. 66E+04
- 6. 66E+04 6.66E+04 3 P-32
- 3. 95E+09 2.46E+OB 1.53E+OB O.OOE+OO O.OOE+OO
- 0. OOE+OO 4.44E+08 4
Cr-51
- 0. OOE+OO O.OOE+OO 5.86E+03 3.50E+03
- 1. 29E+03
- 7. 78E+03
- 1. 47E+06 5 M,-54
- 0. OOE+OO
- 6. 49E+06
- 1. 24E+06 O.OOE+OO
- 1. 93E,t,06 O.OOE+OO
- 1. 99E+07 6 Fe-59
- 2. 14E+08
- 5. 04E+08
- 1. 93E+08 O.OOE+OO O.OOE+OO
- 1. 41 E+08
- 1. 68E+09 7 Co-57
- 0. OOE+OO 4.01E+06 6.66E+06 O.OOE+OO O.OOE+OO O.OOE+OO
- 1. 02E+08 8 Co-58
- 0. OOE+OO
- 1. 42E+07
- 3. 18E+07 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 2. 87E+08 9 Co-60
- 0. OOE+OO
- 5. 12E+07
- 1. 13E+08 O.OOE+OO
- 0. OOE+OO O.OOE+OO 9.61E+OB 10 Zn-65
- 2. 54E+08
- 8. 09E+08 3.66E+08
- 0. OOE+OO 5.41E+08 O.OOE+OO
- 5. 10E+08 11 Se-75 O.OOE+OO
- 1. 21E+08
- 4. 70E+07 O.OOE+OO
- 1. 76E+08 O.OOE+OO
- 1. 75E+07 12 Rb-86 O.OOE+OO
- 4. 11E+08
- 1. 92E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 8. 11 E+07 13 Sr-89 2.41E+08
- O. OOE+OO
- 6. 92E+06
- 0. OOE+OO O.OOE+OO O.OOE+OO 3.87E+07 14 Sr-90 8.41E+09
- 0. OOE+OO
- 2. 06E+09
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 2.43E+08 15 Y-91
- 8. 94E+05 O.OOE+OO
- 2. 39E+04
- 0. OOE+OO O.OOE+OO O.OOE+OO 4.92E-1;08 16 Zr-95
- 1. 47E+06
- 4. 71E+05
- 3. 19E+05
- 0. OOE+OO 7.39E+05 O.OOE+OO 1.49E+09 17 NJ-95
- 1. 89E+06
- 1. 05E+06 5.64E+05
- 0. OOE+OO
- 1. 04E+06 O.OOE+OO 6.37E+09 18 Nb-97
- 5. 32E-119
- 1. 34E-119 4.91E-120
- 0. OOE+OO
- 1. 57E-119 O.OOE+OO
- 4. 96E-116 19 lvb-99 O.OOE+OO 8.51E+04
- 1. 62E+04
- 0. OOE+OO
- 1. 93E+05 O.OOE+OO
- 1. 97E+05 20 Tc-99m
- 3. 83E-21
- 1. 08E-20
- 1. 38E-19 O.OOE+OO
- 1. 64E-19
- 5. 30E-21
- 6. 40E-18 21 Ru-103 8.57E+07 O.OOE+OO 3.69E+07
- 0. OOE+OO 3.27E+08
- 0. OOE+OO
- 1. OOE+10 22 Ru-106
- 1. 97E+09 O.OOE+OO 2.49E+08
- 0. OOE+OO
- 3. 80E+09
- 0. OOE+OO 1.27E+11 23 Ag-110m
- 4. 77E+06
- 4. 41 E+06
- 2. 62E+06 O.OOE+OO 8.67E+06 O.OOE+OO
- 1. 80E+09 24 Sb-124 O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125
- 0. OOE+OO O.OOE+OO 0.00E+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO 27 Te-127m 8.38E+08 3.00E+08
- 1. 02E+OB
- 2. 14E+OB 3.40E+09 O.OOE+OO 2.81E+09 28 Te-129m
- 9. 33E+OB 3.48E+08
- 1. 48E+08
- 3. 21 E+OB
- 3. 89E+09
- 0. OOE+OO
- 4. 70E+09 29 1-131
- 9. 13E+06 1.31E+07 7.48E+06 4.28E+09 2.24E+07 O.OOE+OO 3.45E+06 30 1-133 3.12E-01
- 5. 42E- 01
- 1. 65E-01
- 7. 96E+01
- 9. 46E- 01 O.OOE+OO
- 4. 87E- 01 31 Cs-134
- 4. 53E+08
- 1. 08E+09
- 8. 81 E+08
- 0. OOE+OO 3.49E+08
- 1. 16E+08
- 1. 89E+07 32 Cs-136
- 1. 02E+07 4.04E+07
- 2. 91E+07 O.OOE+OO 2.25E+07 3.08E+06 4.59E+06 33 Cs-137 5.90E+08 8.06E+08 5.28E+08
- 0. OOE+OO
- 2. 74E+08
- 9. 10E+07
- 1. 56E+07 34 Ba-140
- 2. 44E+07
- 3. 06E+04 1.60E+06
- 0. OOE+OO
- 1. 04E+04
- 1. 75E+04 5.02E+07 35 La-140
- 3. 16E-02
- 1. 59E- 02 4.21E-03
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 17E+03 36 Ce-141
- 1. 16E+04
- 7. 83E+03
- 8. 88E+02
- 0. OOE+OO 3.64E+03 O.OOE+OO 2.99E+07 37 Ce-144
- 1. 03E+06 4.32E+05
- 5. 55E+04
- 0. OOE+OO
- 2. 56E+05
- 0. OOE+OO 3.50E+08 Al I nucl ides (except H-3 and C-14) calculated per CDCM equat i on 2. 3-25 1 3 cal cul at ed per CDCM equat i on 2.3-30 C-14 cal cul at ed per ERS-UvR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS
/
Pat hway = rv'l:?at
~e Q-cup = Teen t-tJcl i de 1
H-3 2
C-14 3
P-32 4
Cr-51 5
Ml-54 6
Fe-59 7 Co-57 8 Co-58 9
Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 Nl-95 18 Nl-97 19 fvb-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 1-131 30 I - 133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone O.OOE+OO
- 2. 81E+05
- 3. 34E+09
- 0. OOE+OO
- 0. OOE+OO
- 1. 71 E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 79E+08
- 0. OOE+OO
- 0. OOE+OO
- 2. 03E+08 5.44E+09
- 7. 53E+05
- 1. 18E+06
- 1. 47E+06
- 4. 44E-119
- 0. OOE+OO
- 3. 04E-21
- 6. 98E+07
- 1. 28E+09
- 3. 61E+06
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 7. 07E+08
- 7. 82E+08
- 7. 59E+06
- 2. 61 E- 01
- 3. 60E+08
- 7. 98E+06
- 4. 90E+08 2.02E+07
.2. 60E- 02
- 9. 72E+03
- 8. 72E+05 ATTACHMENT J Page 10 of 19 P&I ORGAN DOSE FACTORS Tabl e 2. 3-11 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrren1yr per uCi/sec)
Liver
- 1. 94E+02 5.62E+04 2.07E+08 O.OOE+OO 4.95E+06
- 4. OOE+08 3.22E+06
- 1. 09E+07 3.97E+07 6.21E+08 1.01E+08 3.43E+08 O.OOE+OO O.OOE+OO O.OOE+OO
- 3. 71E+05
- 8. 17E+05 1.10E-119 7.03E+04
- 8. 48E-21 O.OOE+OO O.OOE+OO 3.42E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.51E+08 2.90E+08
- 1. 06E+07
- 4. 42E- 01 8.48E+08
- 3. 14E+07
- 6. 51E+08
- 2. 47E+04
- 1. 28E- 02
- 6. 49E+03 3.61E+05 i'.
Body
- 1. 94E+02
- 5. 62E+04
- 1. 29E+08
- 4. 69E+03 9.81E+05
- 1. 54E+08 5.40E+06
- 2. 52E+07
- 8. 95E+07 2.90E+08
- 3. 98E+07 1.61E+08 5.83E+06
- 1. 34E+09 2.02E+04
- 2. 55E+05 4.50E+05
- 4. 02E-120
- 1. 34E+04 1.10E-19
- 2. 98E+07
- 2. 09E+08
- 2. 08E+06
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 8.41E+07
- 1. 24E+08
- 5. 71E+06
- 1. 35E- 01
- 3. 93E+08
- 2. 11E+07
- 2. 27E+08
- 1. 30E+06
- 3. 40E-03
- 7. 46E+02
- 4. 68E+04 Thyroid
- 1. 94E+02
- 5. 62E+04 O.OOE+OO 2.60E+03 O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 68E+08
- 2. 52E+08
- 3. 10E+09
- 6. 17E+01
- 0. OOE+OO
- 0. OOE+OO 0.00E+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO Procedure Number:
Unit:
1/2 Revision:
11 Kidney
- 1. 94E+02
- 5. 62E+04 O.OOE+OO
- 1. 03E+03
- 1. 48E+06
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 3. 97E+08
- 1. 49E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 5. 45E+05
- 7. 92E+05
- 1. 29E-119
- 1. 61E+05
- 1. 26E-19 2.46E+08
- 3. 19E+09 6.52E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 2.87E+09
- 3. 27E+09
- 1. 83E+07 7.75E-01 2.69E+08
- 1. 71E+07 2.22E+08 8.38E+03
- 0. OOE+OO 3.06E+03
- 2. 15E+05 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
101 of131 Lung
- 1. 94E+02 5.62E+04
- 0. OOE+OO 6.69E+03
- 0. OOE+OO
- 1. 26E+08
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO,
- 4. 71E-21
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 03E+08
- 2. 69E+06 8.61E+07
- 1. 66E+04
- 0. OOE+OO O.OOE+OO O.OOE+OO G -LLI
- 1. 94E+02
- 5. 62E+04 2.80E+08 7.88E+05
- 1. 01E+07
- 9. 45E+08 6.01E+07
- 1. 51E+08
- 5. 17E+08
- 2. 63E+08
- 1. 03E+07 5.08E+07
- 2. 42E+07
- 1. 53E+08 3.09E+08 8.56E+08 3.49E+09
- 2. 63E-115 1.26E+05
- 5. 57E-18 5.83E+09 7.94E+10 9.60E+08 O.OOE+OO
- 0. OOE+OO 0.00E+OO
- 1. 76E+09
- 2. 93E+09
- 2. 10E+06
- 3. 34E- 01
- 1. 05E+07
- 2. 53E+06 9.27E+06
- 3. 11E+07
- 7. 33E+02 1.86E+07
H-3 cal cul at ed per a:x:::M equat i on 2. 3-30 C-14 cal cul at ed per ERS-UvR- 001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 1 m of n 1 ATTACHMENT J Page 11 of 19 P&I ORGAN DOSE FACTORS Table 2.3-12 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrrem'yr per ua / sec)
Pathway = ti/eat At;Je Q oup = Chi Id l\\tlcl i de Bone Liver T.
Body Thyroid Kidney Lung G -LLI 1
- 0. OOE+OO
- 2. 34E+02
- 2. 34E+02
- 2. 34E+02
- 2. 34E+02
- 2. 34E+02
- 2. 34E+02 2
- 5. 29E+05
- 1. 06E+05
- 1. 06E+05
- 1. 06E+05
- 1. 06E+05
- 1. 06E+05
- 1. 06E+05 3
P-32
- 6. 29E+09 2.94E+08 2.43E+08 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 74E+08 4
Cr-51 O.OOE+OO O.OOE+OO
- 7. 31E+03
- 4. 06E+03
- 1. 11 E+03 7.41E+03
- 3. 88E+05 5 Ml-54
- 0. OOE+OO
- 5. 66E+06
- 1. 51E+06
- 0. OOE+OO 1.59E+06
- 0. OOE+OO
- 4. 75E+06 6
Fe-59
- 3. 04E+08 4.91E+08 2.45E+08
- 0. OOE+OO O.OOE+OO
- 1. 42E+08
- 5. 12E+08 7
- 0. OOE+OO 4.21E+06
- 8. 52E+06 O.OOE+OO O.OOE+OO O.OOE+OO
- 3. 45E+07 8 Co-58
- 0. OOE+OO
- 1. 28E+07
- 3. 91E+07 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO 7.45E+07 9
- 0. OOE+OO
- 4. 72E+07 1.39E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 2. 61E+08 10 Zn-65
- 2. 68E+08
- 7. 15E+08 4.44E+08
- 0. OOE+OO
- 4. 50E+08
- 0. OOE+OO
- 1. 25E+08 11 Se-75
- 0. OOE+OO
- 1. 45E+08 7.49E+07
- 0. OOE+OO
- 1. 96E+08
- 0. OOE+OO
- 6. 72E+06 12 Rb-86
- 0. OOE+OO
- 4. 87E+08
- 2. 99E+08
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 3. 13E+07 13 Sr-89
- 3. 85E+08 O.OOE+OO
- 1. 10E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 49E+07 14 Sr-90
- 7. 03E+09
- 0. OOE+OO
- 1. 78E+09 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 9. 47E+07 15 Y-91
- 1. 42E+06 O.OOE+OO
- 3. 81E+04
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 90E+08 16 Zr-95
- 2. 09E+06
- 4. 59E+05
- 4. 09E+05
- 0. OOE+OO 6.57E+05 O.OOE+OO
- 4. 79E+08 17 N:>- 95
- 2. 54E+06
- 9. 90E+05
- 7. 07E+05
- 0. OOE+OO
- 9. 30E+05 O.OOE+OO
- 1. 83E+09 18 N:,- 97 8.24E-119
- 1. 49E-119 6.95E-120
- 0. OOE+OO 1.65E-119 O.OOE+OO 4.59E-114 19 lvb-99
- 0. OOE+OO
- 9. 79E+04
- 2. 42E+04 O.OOE+OO 2.09E+05 O.OOE+OO
- 8. 09E+04 20 Tc-99m
- 5. 33E-21
- 1. 05E-20 1.73E-19
- 0. OOE+OO
- 1. 52E-19
- 5. 31E-21
- 5. 95E-18 21 Ru-103 1.26E+08 O.OOE+OO
- 4. 85E+07
- 0. OOE+OO
- 3. 18E+08
- 0. OOE+OO 3.26E+09 22 Ru-106
- 3. 12E+09
- 0. OOE+OO
- 3. 89E+08 O.OOE+OO 4.21E+09
- 0. OOE+OO 4.85E+10 23 Ag-110m 5.99E+06
- 4. 04E+06
- 3. 23E+06 O.OOE+OO
- 7. 53E+06
- 0. OOE+OO 4.81E+08 24 Sb-124
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO 25 Sb-125
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO 26 Sb-126
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 27 Te-127m
- 1. 33E+09 3.59E+08
- 1. 58E+08
- 3. 19E+08 3.80E+09
- 0. OOE+OO
- 1. 08E+09 28 Te-129m
- 1. 47E+09
- 4. 11E+08
- 2. 29E+08
- 4. 75E+08 4.33E+09 O.OOE+OO
- 1. 80E+09 29 1-131
- 1. 41E+07
- 1. 42E+07
- 8. 04E+06 4.68E+09 2.32E+07
- 0. OOE+OO 1; 26E+06 30 1-133
- 4. 84E- 01
- 5. 99E- 01
- 2. 27E- 01
- 1. 11 E+02
- 9. 98E- 01
- 0. OOE+OO 2.41E-01 31 Cs-134 6.35E+08
- 1. 04E+09 2.20E+08
- 0. OOE+OO 3.23E+08
- 1. 16E+08 5.62E+06 32 Cs-136
- 1. 38E+07
- 3. 78E+07
- 2. 45E+07
- 0. OOE+OO 2.01E+07
- 3. OOE+06
- 1. 33E+06 33 Cs-137
- 9. 02E+08 8.63E+08
- 1. 27E+08
- 0. OOE+OO
- 2. 81E+08 1.01E+08 5.40E+06 34 Ba-140
- 3. 72E+07
- 3. 26E+06
- 2. 17E+06
- 0. OOE+OO
- 1. 06E+04
- 1. 94E+04
- 1. 89E+07 35 La-140
- 4. 76E- 02
- 1. 66E- 02 5.61E-03
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 4.63E+02 36 C.e-141
- 1. 83E+04
- 9. 13E+03
- 1. 36E+04 O.OOE+OO 4.00E+03 O.OOE+OO
- 1. 14E+07 37 C.e-144
- 1. 64E+06
- 5. 15E+05
- 8. 77E+04 O.OOE+OO 2.85E+05
- 0. OOE+OO
- 1. 34E+08 Al I nucl ides (except H-3 and C-14) cal cul at ed per CDCM equat i on 2. 3-25 H-3 cal cul at ed per CDCM equat i on 2. 3-30 C-14 cal cul at ed per ERS-UvR- 001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 l(n oflil ATTACHMENT J Page 12 of 19 P&I ORGAN DOSE FACTORS Table 2.3-13 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrrentyr per uCi I sec)
Pat hway = Cow M I k Age Q-oup = Adu I t Mlclide Bone Liver T. Body Thyroid Ki dney Lung G -LLI 1 H-3
- 0. OOE+OO
- 7. 63E+02
- 7. 63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 2 C-14 3.63E+05 7.26E+04
- 7. 26E+04
- 7. 26E+04 7.26E+04 7.26E+04 7.26E+04 3 P-32 1.45E+10 9.01E+08
- 5. 60E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 63E+09 4
Cr-51
- 0. OOE+OO
- 0. OOE+OO
- 2. 38E+04
- 1. 42E+04 5.24E+03
- 3. 15E+04 5.98E+06 5 M,-54 O.OOE+OO 5.95E+06
- 1. 13E+06
- 0. OOE+OO
- 1. 77E+06
- 0. OOE+OO
- 1. 82E+07 6 Fe-59
- 2. 40E+07
- 5. 63E+07
- 2. 16E+07
- 0. OOE+OO O.OOE+OO
- 1. 57E+07 1.88E+08 7 Co-57 O.OOE+OO
- 9. 10E+05
- 1. 51 E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 2. 31E+07 8 Co-58 O.OOE+OO 3.67E+06
- 8. 22E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 7.43E+07 9 Co-60 O.OOE+OO
- 1. 12E+07
- 2. 46E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 2. 10E+08 10 Zn-65
- 9. 80E+08
- 3. 12E+09 1.41E+09
- 0. OOE+OO 2.09E+09
- 0. OOE+OO
- 1. 96E+09 11 Se-75 O.OOE+OO
- 1. 14E+09
- 4. 41 E+08
- 0. OOE+OO
- 1. 65E+09
- 0. OOE+OO
- 1. 64E+08 12 Rb-86
- 0. OOE+OO
- 2. 19E+09
- 1. 02E+09
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 4. 32E+08 13 Sr-89
- 1. 16E+09 O.OOE+OO 3.33E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 86E+08 14 Sr-90
- 3. 16E+10 O.OOE+OO
- 7. 76E+09
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 9. 14E+08 15 Y-91
- 6. 78E+03
- 0. OOE+OO
- 1. 81E+02
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 3. 73E+06 16 Zr-95
- 7. 40E+02 2.37E+02
- 1. 61 E+02
- 0. OOE+OO
- 3. 72E+02
- 0. OOE+OO 7.52E+05 17 N:>- 95
- 6. 77E+04
- 3. 77E+04
- 2. 03E+04
- 0. OOE+OO
- 3. 72E+04
- 0. OOE+OO 2.29E+08 18 N:>-97 2.81E-12
- 7. 11 E-13
- 2. 60E-13
- 0. OOE+OO
- 8. 30E-13
- 0. OOE+OO
- 2. 62E- 09 19 fvb~ 99 O.OOE+OO
- 2. 11E+07 4.01E+06
- 0. OOE+OO
- 4. 77E+07 O.OOE+OO
- 4. 88E+07 20 Tc-99m
- 2. 83E+OO
- 7. 99E+OO
- 1. 02E+02
- 0. OOE+OO
- 1. 21E+02
- 3. 91E+OO
- 4. 73E+03 21 Ru-103
- 8. 29E+02 O.OOE+OO 3.57E+02 O.OOE+OO
- 3. 16E+03
- 0. OOE+OO 9.68E+04 22 Ru-106
- 1. 43E+04 0.00E+OO 1.81E+03
- 0. OOE+OO
- 2. 77E+04 O.OOE+OO 9.27E+05 23 Ag-110m
- 4. 16E+07
- 3. 84E+07 2.28E+07
- 0. OOE+OO 7.56E+07
- 0. OOE+OO
- 1. 57E+10 24 Sb-124 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO 25 Sb-125
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO 26 Sb-126 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO 27 Te-127m 3.44E+07
- 1. 23E+07
- 4. 19E+06
- 8. 79E+06
- 1. 40E+08 O.OOE+OO
- 1. 15E+08 28 Te-129m 4.95E+07
- 1. 85E+07
- 7. 84E+06
- 1. 70E+07 2.07E+08 O.OOE+OO 2.49E+08 29 I - 131
- 2. 52E+08
- 3. 60E+08
- 2. 06E+OB
- 1. 18E+11
- 6. 17E+OB
- 0. OOE+OO
- 9. 50E+07 30 1-133 3.29E+06
- 5. 72E+06
- 1. 75E+06 8.41E+OB 9.99E+06
- 0. OOE+OO.
- 5. 14E+06 31 Cs-134 3.89E+09 9.27E+09
- 7. 58E+09
- 0. OOE+OO
- 3. OOE+09 9.96E+08
- 1. 62E+08 32 Cs-136 2.23E+08
- 8. 82E+08
- 6. 35E+08
- 0. OOE+OO 4.91E+08
- 6. 73E+07
- 1. OOE+08 33 Cs-137
- 4. 99E+09
- 6. 82E+09 4.47E+09
- 0. OOE+OO
- 2. 32E+09
- 7. 70E+OB
- 1. 32E+OB 34 Ba-140 2.28E+07 2.87E+04
- 1. 49E+06
- 0. OOE+OO
- 9. 74E+03
- 1. 64E+04
- 4. 70E+07 35 La-140 3.84E+OO
- 1. 93E+OO 5.11E-01 0.00E+OO O.OOE+OO O.OOE+OO 1.42E+05 36 Ce-141 3.99E+03
- 2. 70E+03
- 3. 06E+02
- 0. OOE+OO
- 1. 25E+03 O.OOE+OO
- 1. 03E+07 37 Ce-144 2.54E+05
- 1. 06E+05
- 1. 36E+04 O.OOE+OO 6.29E+04
- 0. OOE+OO
- 8. 58E+07 Al I nuclides (except H-3 and C-14) calculated per CDCM equation 2.3-24 H-3 cal cul at ed per ClJCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LI\\.R- 001
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 104 of Bl ATTACHMENT J Page 13 of 19 P&I ORGAN DOSE FACTORS Table 2.3-14 R VALUES FCR BEAVER VALLEY SI TE
{ sq rret er - rrr em' yr per ua / sec)
Pathway = Cow MI k Age G-oup = Teen Nuclide Bone Liver T. Body Thyroid Ki dney Lung GI - LLI 1 H-3
- 0. OOE+OO
- 9. 94E+02 9.94E+02 9.94E+02
- 9. 94E+02
- 9. 94E+02
- 9. 94E+02 2 C-14
- 6. 70E+05
- 1. 34E+05
- 1. 34E+05
- 1. 34E+05
- 1. 34E+05
- 1. 34E+05
- 1. 34E+05 3 P-32
- 2. 67E+10
- 1. 66E+09
- 1. 04E+09
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 2.25E+09 4 Cr-51 O.OOE+OO O.OOE+OO
- 4. 15E+04
- 2. 31 E+04
- 9. 1 OE+03 5.93E+04 6.97E+06 5 Ml-54 O.OOE+OO
- 9. 91E+06
- 1. 96E+06 O.OOE+OO
- 2. 95E+06
- 0. OOE+OO 2.03E+07 6 Fe-59
- 4. 18E+07
- 9. 76E+07
- 3. 77E+07 O.OOE+OO
- 0. OOE+OO
- 3. 08E+07
- 2. 31E+08 7 Co-57 O.OOE+OO
- 1. 60E+06 2.68E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E+07 8 Co-58
- 0. OOE+OO
- 6. 17E+06
- 1. 42E+07
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 8.51E+07 9 Co-60
- 0. OOE+OO
- 1. 89E+07
- 4. 26E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 2.46E+08 10 Zn-65
- 1. 51 E+09 5.23E+09
- 2. 44E+09
- 0. OOE+OO
- 3. 34E+09 O.OOE+OO 2.21E+09 11 Se-75
- 0. OOE+OO 2.08E+09
- 8. 15E+08
- 0. OOE+OO
- 3. 05E+09 O.OOE+OO
- 2. 12E+08 12 Rb-86
- 0. OOE+OO
- 3. 99E+09
- 1. 87E+09
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 5.91E+08 13 Sr-89
- 2. 14E+09
- 0. OOE+OO
- 6. 12E+07
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 2.55E+08 14 Sr-90
- 4. 47E+10
- 0. OOE+OO
- 1. 10E+10
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 1.25E+09 15 Y-91
- 1. 25E+04 O.OOE+OO
- 3. 35E+02
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 5. 11E+06 16 Zr-95
- 1. 29E+03
- 4. 08E+02 2.81E+02
- 0. OOE+OO 6.00E+02 O.OOE+OO 9.42E+05 17 l\\b-95
- 1. 16E+05 6.41E+04 3.53E+04 O.OOE+OO
- 6. 21 E+04 O.OOE+OO
- 2. 74E+08 18 l'Jb-97
- 5. 13E-12
- 1. 27E-12
- 4. 65E-13 O.OOE+OO
- 1. 49E-12 O.OOE+OO
- 3. 04E- 08 19 fllb-99
- 0. OOE+OO
- 3. 80E+07 7.25E+06
- 0. OOE+OO
- 8. 70E+07 O.OOE+OO 6.81E+07 20 Tc-99m
- 4. 90E+OO
- 1. 37E+01
- 1. 77E+02
- 0. OOE+OO
- 2. 04E+02 7.59E+OO 8.98E+03 21 Ru-103
- 1. 47E+03 O.OOE+OO
- 6. 30E+02 O.OOE+OO
- 5. 20E+03 O.OOE+OO
- 1. 23E+05 22 Ru-106
- i. 03E+04 O.OOE+OO 3.32E+03 O.OOE+OO
- 5. 08E+04 O.OOE+OO 1.26E+06 23 Ag-110m 6.87E+07 6.50E+07
- 3. 95E+07
- 0. OOE+OO
- 1. 24E+08 O.OOE+OO
- 1. 83E+10 24 Sb-124
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 26 Sb-126
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m
- 6. 34E+07 2.25E+07
- 7. 54E+06 1.51E+07
- 2. 57E+08
- 0. OOE+OO
- 1. 58E+08 28 Te-129m
- 9. 06E+07 3.36E+07
- 1. 43E+07 2.92E+07
- 3. 79E+08
- 0. OOE+OO 3.40E+08 29 1-131
- 4. 57E+08 6.39E+08
- 3. 43E+08
- 1. 87E+11
- 1. 10E+09 O.OOE+OO 1.26E+08 30 1-133
- 6. 01E+06
- 1. 02E+07
- 3. 11 E+06
- 1. 42E+09
- 1. 79E+07 O.OOE+OO
- 7. 71E+06 31 Cs-134
- 6. 76E+09
- 1. 59E+10
- 7. 38E+09 O.OOE+OO 5.06E+09
- 1. 93E+09
- 1. 98E+08 32 Cs-136
- 3. 80E+08
- 1. 50E+09
- 1. 01E+09
- 0. OOE+OO
- 8. 15E+08
- 1. 28E+08 1.20E+08 33 Cs-137
- 9. 05E+09 1.20E+10
- 4. 19E+09
- 0. OOE+OO
- 4. 10E+09
- 1. 59E+09
- 1. 71E+08 34 Ba-140
- 4. 12E+07 5.05E+04 2.65E+06 O.OOE+OO
- 1. 71 E+04
- 3. 39E+04 6.35E+07 35 La-140
- 6. 89E+OO 3.39E+OO
- 9. 01E-01
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 94E+05 36 Ce-141 7.32E+03
- 4. 89E+03 5.62E+02
- 0. OOE+OO
- 2. 30E+03 O.OOE+OO 1.40E+07 37 Ce-144 4.67E+05
- 1. 93E+05
- 2. 51 E+04 O.OOE+OO
- 1. 15E+05 O.OOE+OO
- 1. 17E+08 Al I nucl ides (except H-3 and C-14) calculated per CDCM equat i on 2. 3-24 H-3 cal cul at ed per CXlCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LIVR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = Cow M I k
. Age Q-oup = O,i Id Nuclide 1
M,- 54 6 Fe-59 7 Co-57 8 Co-58 9 Co-60 10 Zri-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 Nb-95 18 Nb-97 19 fvb-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 I -133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La: 140 36 Ce-141 37 Ce-144 Bone O. OOE+OO
- 1. 65E+06 6.59E+10 O. OOE+OO
- 0. OOE+OO
- 9. 70E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.95E+09 O.OOE+OO O.OOE+OO 5.29E+09 7.55E+10 3.08E+04 3.00E+03
- 2. 61 E+05 1.25E-11
- 0. OOE+OO 1.12E+01 3.49E+03 6.49E+04
- 1. 49E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 56E+08
- 2. 23E+08
- 1. 11 E+09
- 1. 46E+07
- 1. 56E+10 8.58E+08
- 2. 18E+10
- 9. 94E+07
- 1. 65E+01 1.80E+04
- 1. 15E+06 ATTACHMENT J Page 14 of 19 P&I ORGAN DOSE FACTORS Table 2.3-15 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er-rrr ent yr per uCi / sec)
Liver
- 1. 57E+03 3.29E+05 3.09E+09
- 0. OOE+OO
- 1. 48E+07
- 1. 57E+08
- 2. 73E+06 9.43E+06
- 2. 94E+07 7.87E+09
- 3. 89E+09
- 7. 40E+09 O.OOE+OO O.OOE+OO O.OOE+OO 6.60E+02
- 1. 02E+05
- 2. 25E-12
- 6. 92E+07 2.20E+01 O.OOE+OO 0.00E+OO 1.01E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.21E+07 6.24E+07
- 1. 11E+09 1.81E+07 2.56E+10 2.36E+09 2.09E+10
- 8. 71E+06
- 5. 77E+OO
- 8. 99E+03 3.61E+05 T. Body
- 1. 57E+03
- 3. 29E+05 2.54E+09
- 8. 46E+04 3.95E+06
- 7. 82E+07 5.52E+06 2:80E+07 8.67E+07 4.89E+09 2.01E+09 4.55E+09 1.51E+08
- 1. 91E+10 8.24E+02 5.88E+02 7.26E+04
- 1. 05E-12
- 1. 71E+07 3.65E+02
- 1. 34E+03
- 8. 10E+03 8.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO
- 1. 86E+07 3.47E+07
- 6. 33E+08 6.83E+06 5.40E+09
- 1. 53E+09
- 3. 08E+09 5.80E+06
- 1. 94E+OO
- 1. 34E+04
- 6. 15E+04 Thyroid 1.57E+03 3.29E+05 O.OOE+OO
- 4. 70E+04
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+oo*
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 3. 74E+07 7.20E+07
- 3. 68E+11
- 3. 36E+09
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO Procedure Number:
Unit:
1/2 Revision:
11 Kidney
- 1. 57E+03 3.29E+05 O.OOE+OO
- 1. 28E+04
- 4. 16E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 4. 96E+09 5.26E+09 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+QO 9.45E+02
- 9. 54E+04 2.50E-12
- 1. 48E+08 3.20E+02
- 8. 78E+03
- 8. 76E+04
- 1. 87E+08 O.OOE+OO
- 0. OOE+OO O.OOE+OO 4.46E+08
- 6. 56E+08
- 1. 83E+09 3.01E+07 7.93E+09
- 1. 26E+09
- 6. 80E+09
- 2. 84E+04
- 0. OOE+OO 3.94E+03 2.00E+05 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
10S of Bl Lung
- 1. 57E+03 3.29E+05
- 0. OOE+OO 8.58E+04 O.OOE+OO 4.55E+07 O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.12E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 2.85E+09
- 1. 87E+08 2.45E+09
- 5. 19E+04 O.OOE+OO O.OOE+OO O.OOE+OO G-LLI 1.57E+03 3.29E+05
- 1. 82E+09
- 4. 49E+06
- 1. 24E+07
- 1. 63E+08 2.24E+07
- 5. 50E+07
- 1. 63E+08 1.38E+09
- 1. 80E+08
- 4. 76E+08 2.05E+08
- 1. 02E+09
- 4. 11E+06 6.89E+05
- 1. 88E+08
- 6. 94E- 07
- 5. 72E+07
- 1. 25E+04 9.01E+04
- 1. 01E+06
- 1. 20E+10 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 27E+08
- 2. 72E+08 9.92E+07 7.28E+06
- 1. 38E+08 8.29E+07
- 1. 31E+08 5.04E+07
- 1. 61E+05
- 1. 12E+07 9.41E+07 Al I nucl ides ( except H-3 and C-14) cal cul at ed per CDCM equation 2. 3-24 H-3 cal cul at ed per CDCM equat i on 2. 3-28 C-14 calculated per ERS-UvR-001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = Cow M I k Age G" oup = I nf ant Nuclide 1 H-3 2 C-14 3 P-32 4
Cr - 51 5 M,- 54 6 Fe-59 7 Co-57 8 Co-58 9 Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 f\\l:>- 95 18 N:>- 97 19 M:>- 99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 1-131 30 I - 133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone
- 0. OOE+OO
- 3. 23E+06 1.36E+11 O.OOE+OO
- 0. OOE+OO
- 1. 81E+08
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 3. 97E+09
- 0. OOE+OO
- 0. OOE+OO
- 1. 01E+10
- 8. 22E+10
- 5. 79E+04 5.33E+03
- 4. 87E+05
- 2. 63E-11 O.OOE+OO
- 2. 34E+01 7.06E+03
- 1. 34E+05
- 2. 75E+08 O.OOE+OO O.OOE+OO O.OOE+OO
- 3. 16E+08 4.58E+08 2.31E+09
- 3. 08E+07 2.51E+10
- 1. 68E+09 3.48E+10
- 2. 05E+08 3.45E+01 3.57E+04
- 1. 65E+06 ATTACHMENTJ Page 15 of 19 P&I ORGAN DOSE FACTORS Table 2.3-16 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrrerrlyr per uCi/sec)
U ver
- 2. 38E+03
- 6. 89E+05
- 7. 99E:!-09
- 0. OOE+OO
- 2. 76E+07
- 3. 16E+08
- 6. 36E+06
- 1. 89E+07 6.00E+07
- 1. 36E+10
- 9. 61 E+09
- 1. 88E+10
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 30E+03
- 2. 01 E+05
- 5. 62E-12
- 1. 77E+08
- 4. 82E+01
- 0. OOE+OO
- 0. OOE+OO 2.01E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 05E+08
- 1. 57E+08
- 2. 72J::+09 4.49E+07 4.69E+10
- 4. 93E+09
- 4. 07E+10 2.05E+05
- 1. 36E+01
- 2. 18E+04
- 6. 75E+05 T. Body
- 2. 38E+03
- 6. 89E+05 5.27E+09
- 1. 34E+05
- 6. 25E+06
- 1. 25E+08
- 1. 03E+07
- 4. 70E+07
- 1. 42E+08 6.27E+09
- 4. 13E+09 9.28E+09
- 2. 89E+08
- 2. 09E+10
- 1. 54E+03 9.22E+02
- 1. 16E+05
- 2. 03E-12
- 3. 45E+07 6.21E+02
- 2. 36E+03
- 1. 67E+04
- 1. 33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.83E+07
- 7. 06E+07
- 1. 20E+09
- 1. 31E+07
- 4. 73E+09
- 1. 84E+09
- 2. 89E+09
- 1. 05E+07 3.50E+OO 2.57E+03 9.25E+04 Thyroid
- 2. 38E+03 6.89E+05
- 0. OOE+OO
- 8. 75E+04 O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 9. 14E+07
- 1. 76E+08
- 8. 95E+11
- 8. 17E+09
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO Procedure Number:
Unit:
1/2 Revision:
11 Kidney 2.38E+03 6.89E+05 O.OOE+OO
- 1. 91E+04
- 6. 11E+06 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 6.60E+09
- 9. 31E+09
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 1.40E+03
- 1. 44E+05
- 4. 39E-12 2.64E+08
- 5. 19E+02 1.47E+04
- 1. 58E+05
- 2. 88E+08 O.OOE+OO O.OOE+OO O.OOE+OO
- 7. 79E+08
- 1. 15E+09
- 3. 18E+09
- 5. 28E+07 1.21E+10
- 1. 97E+09
- 1. 09E+10 4.86E+04 O.OOE+OO
- 6. 72E+03
- 2. 73E+05 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
1 Of; of 131 Lung 2.38E+03 6.89E+05 O.OOE+OO
- 1. 70E+05 O.OOE+OO 9.35E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 2. 52E+01 O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO 4.95E+09 4.02E+08 4.43E+09
- 1. 26E+05 O.OOE+OO
- 0. OOE+OO O.OOE+OO GI - LLI
- 2. 38E+03
- 6. 89E+05
- 1. 84E+09
- 3. 91E+06
- 1. 01E+07
- 1. 51E+08
- 2. 17E+07
- 4. 70E+07
- 1. 43E+08
- 1. 15E+10
- 1. 79E+08
- 4. 81E+08 2.07E+08
- 1. 03E+09
- 4. 15E+06 6.47E+05
- 1. 69E+08
- 1. 77E- 06 5.83E+07
- 1. 40E+04
- 8. 59E+04 1.01E+06
- 1. 04E+10
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 28E+08
- 2. 74E+08
- 9. 72E+07 7.60E+06 1.27E+08 7.49E+07
- 1. 27E+08 5.02E+07
- 1. 60E+05
- 1. 13E+07 9.47E+07 Al I nucl i des ( except H-3 and C-14) cal cul at ed per CDCM equat i on 2. 3-24 H-3 cal cul at ed per CDCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LrvR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = Goat M I k Age Q oup = Adul t Nuclide 1 H-3 2 C-14 3 P-32 4 Cr-51 5 Ml-54 6 Fe-59 7 Co-57 8 Co-58 9 Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr - 89 14 Sr-90 15 Y-91 16 Zr-95 17 N:>-95 18 N:>- 97 19 l'vb-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 1-133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone
- 0. OOE+OO 4.36E+04
- 1. 74E+09 O.OOE+OO O.OOE+OO 2.88E+06 O.OOE+OO O.OOE+OO O.OOE+OO
- 1. 18E+08 O.OOE+OO
- 0. OOE+OO
- 1. 39E+08
- 3. 80E+09
- 8. 14E+02
- 8. 87E+01
- 8. 13E+03
- 3. 38E-13
- 0. OOE+OO
- 3. 39E- 01 9.95E+01
- 1. 72E+03
- 4. 99E+06
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 4. 13E+06
- 5. 94E+06
- 3. 02E+07
- 3. 95E+05
- 4. 67E+08
- 2. 68E+07
- 5. 99E+08
- 2. 74E+06
- 4. 60E- 01
- 4. 79E+02
- 3. 05E+04 ATTACHMENT]
Page 16 of 19 P&I ORGAN DOSE FACTORS Table 2.3-17 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er-rrr em yr per ua I sec)
Liver
- 9. 15E+01
- 8. 72E+03
- 1. 08E+08 O.OOE+OO
- 7. 14E+05
- 6. 76E+06 1.09E+05 4.40E+05
- 1. 34E+06
- 3. 74E+08
- 1. 36E+08 2.63E+08 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 2. 85E+01
- 4. 52E+03
- 8. 54E-14
- 2. 53E+06
- 9. 59E- 01 O.OOE+OO
- 0. OOE+OO
- 4. 61E+06
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 48E+06 2.22E+06
- 4. 32E+07
- 6. 87E+05
- 1. 11 E+09 1.06E-1'08
- 8. 19E+08 3.44E+03
- 2. 32E- 01
- 3. 24E+02
- 1. 27E+04 T. Body
- 9. 15E+01
- 8. 72E+03
- 6. 72E+07
- 2. 85E+03
- 1. 36E+05
- 2. 59E+06
- 1. 82E+05
- 9. 86E+05
- 2. 96E+06
- 1. 69E+08 5.29E+07
- 1. 22E+08 3.99E+06
- 9. 32E+08
- 2. 18E+01
- 1. 93E+01 2.43E+03
- 3. 12E-14
- 4. 81E+05
- 1. 22E+01 4.29E+01
- 2. 18E+02
- 2. 74E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 5. 03E+05
- 9. 41 E+05
- 2. 48E+07 2.09E+05
- 9. 09E+08
- 7. 62E+07
- 5. 36E+08
- 1. 79E+05
- 6. 13E- 02
- 3. 68E+01
- 1. 64E+03 Thyroid
- 9. 15E+01
- 8. 72E+03
- 0. OOE+OO
- 1. 70E+03
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 05E+06
- 2. 04E+06
- 1. 42E+10
- 1. 01E+08
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 0.00E+OO Procedure Number:
Unit:
1/2 Revision:
11 Ki dney
- 9. 15E+01
- 8. 72E+03 O.OOE+OO 6.28E+02
- 2. 12E+05
- 0. OOE+OO O.OOE+OO o: OOE+OO
- 0. OOE+OO 2.50E+08
- 1. 98E+08 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 4.47E+01
- 4. 47E+03
- 9. 96E-14
- 5. 72E+06
- 1. 46E+01
- 3. 80E+02
- 3. 32E+03
- 9. 07E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E+07 2.48E+07 7.40E+07
- 1. 20E+06 3.60E+08 5.89E+07
- 2. 78E+08
- 1. 17E+03 O.OOE+OO
- 1. 51E+02 7.55E+03 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
107 of 131 Lung
- 9. 15E+01
- 8. 72E+03
- 0. OOE+OO
- 3. 78E+03
- 0. OOE+OO
- 1. 89E+06 O.OOE+OO O. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 4. 70E- 01
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 19E+08
- 8. 07E+06 9.24E+07
- 1. 97E+03 O.OOE+OO
- 0. OOE+OO O.OOE+OO GI - LLI
- 9. 15E+01
- 8. 72E+03
- 1. 96E+08
- 7. 17E+05
- 2. 19E+06 2.25E+07
- 2. 77E+06 8.91E+06 2.52E+07 2.36E+08
- 1. 97E+07
- 5. 18E+07 2.23E+07
- 1. 10E+08 4.48E+05
- 9. 02E+04
- 2. 74E+07
- 3. 15E-10 5.86E+06 5.67E+02
- 1. 16E+04
- 1. 11 E+05 1.88E+09 O.OOE+OO
- 0. OOE+OO 0.00E+OO
- 1. 38E+07
- 2. 99E+07
- 1. 14E+07
- 6. 17E+05
- 1. 95E+07 1.20E+07
- 1. 59E+07 5.64E+06
- 1. 70E+04
- 1. 24E+06
- 1. 03E+07 Al I nucl i des ( except H-3 and C-14) cal cul at ed per CDCM equat i on 2. 3-24 H-3 cal cul at ed per CDCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LI\\IR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = <?oat M I k Age G-oup = Teen Nuclide 1
Cr-51 5 Ml-54 6 Fe-59 7 Co-57 8 Co-58 9 Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 Nb-95 18 l\\b-97 19 lvb-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 I -133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone
- 0. OOE+OO
- 8. 04E+04 3.21E+09
- 0. OOE+OO
- 0. OOE+OO
- 5. 02E+06 O.OOE+OO
- 0. OOE+OO O.OOE+OO 1.81E+08 O.OOE+OO O.OOE+OO
- 2. 56E+08
- 5. 36E+09
- 1. 50E+03
- 1. 55E+02
- 1. 39E+04
- 6. 15E-13 O.OOE+OO
- 5. 88E- 01
- 1. 77E+02 2.44E+03
- 8. 24E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO 7.61E+06
- 1. 09E+07 5.48E+07 7.21E+05 8.11E+08 4.56E+07
- 1. 09E+09
- 4. 94E+06
- 8. 27E- 01
- 8. 79E+02 5.60E+04 ATTACHMENT J Page17of19 P&I ORGAN DOSE FACTORS Table 2.3-18 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrrem'yr per uCi/sec)
Liver
- 1. 19E+02
- 1. 61E+04
- 1. 99E+08
- 0. OOE+OO
- 1. 19E+06
- 1. 17E+07
- 1. 92E+05 7.40E+05
- 2. 27E+06
- 6. 27E+08 2.49E+08
- 4. 79E+08
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 4. 90E+01 7.69E+03 1.53E-13 4.56E+06 1.64E+OO
- 0. OOE+OO O.OOE+OO 7.80E+06
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 2. 70E+06
- 4. 03E+06 7.67E+07
- 1. 22E+06
- 1. 91E+09
- 1. 80E+08
- 1. 44E+09
- 6. 06E+03
- 4. OGE- 01 5.87E+02 2.32E+04 T. Body
- 1. 19E+02
- 1. 61 E+04
- 1. 24E+08
- 4. 98E+03
- 2. 36E+05
- 4. 52E+06 3.21E+05 1.71E+06
- 5. 11 E+06
- 2. 93E+08
- 9. 78E+07 2.25E+08
- 7. 34E+06
- 1. 32E+09
- 4. 01E+01
- 3. 37E+01 4.23E+03
- 5. 57E-14
- 8. 70E+05
- 2. 13E+01
- 7. 56E+01
- 3. 98E+02
- 4. 75E+06
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 9. 05E+05
- 1. 72E+06
- 4. 12E+07
- 3. 73E+05 8.86E+08
- 1. 21E+08 5.03E+08
- 3. 18E+05
- 1. 08E-01
- 6. 74E+01
- 3. 01E+03 Thyroid
- 1. 19E+02
- 1. 61E+04 O.OOE+OO
- 2. 77E+03
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 81E+06
- 3. 51E+06
- 2. 24E+10
- 1. 71E+08
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO Procedure Number:
Unit:
1/2 Revision:
11 Kidney
- 1. 19E+02
- 1. 61E+04 O.OOE+OO
- 1. 09E+03 3.55E+05 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 4. 01E+08 3.66E+08 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 7. 19E+01 7.45E+03
- 1. 79E-13
- 1. 04E+07 2.45E+01
- 6. 24E+02
- 6. 10E+03
- 1. 49E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 3.08E+07
- 4. 55E+07
- 1. 32E+08
- 2. 15E+06
- 6. 07E+08
- 9. 78E+07
- 4. 91E+08
- 2. 05E+03
- 0. OOE+OO
- 2. 76E+02
- 1. 39E+04 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
108 of 131 Lung
- 1. 19E+02
- 1. 61E+04
- 0. OOE+OO
- 7. 11E+03
- 0. OOE+OO 3.69E+06 O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO 9.11E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2. 32E+08
- 1. 54E+07
- 1. 91E+08 4.. 07E+03 O.OOE+OO O.OOE+OO 0.00E+OO GI - LLI
- 1. 19E+02
- 1. 61E+04
- 2. 70E+08 8.37E+05 2.44E+06
- 2. 77E+07
- 3. 57E+06
- 1. 02E+07
- 2. 96E+07 2.66E+08 2.54E+07
- 7. 09E+07
- 3. 05E+07
- 1. 51E+08
- 6. 14E+05
- 1. 13E+05 3.29E+07
- 3. 65E- 09
- 8. 17E+06
- 1. 08E+03
- 1. 48E+04
- 1. 52E+05
- 2. 19E+09 O.OOE+OO
- 0. OOE+OO O.OOE+OO 1.90E+07 4.08E+07
- 1. 52E+07 9.26E+05
- 2. 38E+07 1.45E+07
- 2. 06E+07 7.62E+06 2.33E+04 1.68E+06
- 1. 41E+07 Al I nucl i des ( except H-3 and C-14) cal cul at ed per CDCM equation 2. 3-24 H-3 cal cul at ed per CDCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LI\\IR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = Goat M I k Age G-oup = O,i Id Nuclide 1 H-3 2 C-14 3, P-32 4
(::r - 51 5
M,- 54 6
Fe-59 7 Co-57 8 Co-58 9 Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 N:>- 95 18 N:>-97 19 l'vb-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 I - 133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone
- 0. OOE+OO
- 1. 98E+05
- 7. 91E+09
- 0. OOE+OO O.OOE+OO
- 1. 16E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 3. 54E+08 O.OOE+OO
- 0. OOE+OO 6.35E+08
- 9. 06E+09 3.70E+03 3.60E+02
- 3. 13E+04
- 1. 49E-12
- 0. OOE+OO 1.35E+OO
- 4. 18E+02
- 7. 79E+03
- 1. 79E+07 O.OOE+OO O.OOE+OO 0.00E+OO 1.88E+07 2.68E+07
- 1. 33E+08
- 1. 75E+06
- 1. 87E+09
- 1. 03E+08 2.62E+09
- 1. 19E+07 1.98E+OO
- 2. 16E+03
- 1. 38E+05 ATTACHMENT J Page 18 of 19 P&I ORGAN DOSE FACTORS Table 2.3-19 R VALUES FCR BEAVER VALLEY SI TE (sq rreter-rrrem'yr per ua/sec)
Liver
- 1. 88E+02
- 3. 95E+04
- 3. 70E+08
- 0. OOE+OO
- 1. 78E+06
- 1. 88E+07
- 3. 27E+05
- 1. 13E+06 3.53E+06
- 9. 44E+08
- 4. 66E+08
- 8. 88E+08 0.00E+OO O.OOE+OO O.OOE+OO
- 7. 92E+01
- 1. 22E+04
- 2. 70E-13
- 8. 30E+06 2.65E+OO O.OOE+OO O.OOE+OO
- 1. 21E+07 O.OOE+OO O.OOE+OO 0.00E+OO 5.05E+06 7.48E+06
- 1. 34E+08
- 2. 17E+06 3.07E+09 2.83E+08 2.50E+09
- 1. 05E+06
- 6. 92E- 01
- 1. 08E+03 4.33E+04 T. Body 1.88E+02
- 3. 95E+04 3.05E+08 1.02E+04
- 4. 74E+05
- 9. 38E+06 6.63E+05 3.46E+06 1.04E+07
- 5. 87E+08 2.41E+08 5.46E+08 1.81E+07 2.30E+09 9.89E+01 7.05E+01
- 8. 71E+03
- 1. 26E-13 2.05E+06 4.39E+01 1.61E+02
- 9. 72E+02 9.65E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.23E+06
- 4. 16E+06 7.60E+07 8.20E+05 6.48E+08
- 1. 83E+08 3.69E+08 6.96E+05
- 2. 33E- 01
- 1. 60E+03 7.37E+03 Thyroid
- 1. 88E+02 3.95E+04 O.OOE+OO
- 5. 64E+03 O.OOE+OO
- 0. OOE+OO 0.00E+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO 4.48E+06
- 8. 64E+06 4.42E+10
- 4. 03E+08 O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO Procedure Number:
Unit:
112 Revision:
11 Kidney 1.88E+02 3.95E+04
- 0. OOE+OO 1.54E+03 4.99E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.95E+08 6.31E+08 O.OOE+OO 0.00E+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 13E+02
- 1. 14E+04 2.99E-13
- 1. 77E+07 3.84E+01 1.05E+03 1.05E+04 2.25E+07
- 0. OOE+OO O.OOE+OO O.OOE+OO 5.35E+07
- 7. 87E+07
- 2. 19E+08 3.61E+06
- 9. 52E+08
- 1. 51E+08
- 8. 16E+08 3.40E+03
- 0. OOE+OO
- 4. 73E+02 2.40E+04 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
]OQ of 131 Lung
- 1. 88E+02 3.95E+04 O.OOE+OO
- 1. 03E+04 O.OOE+OO
- 5. 46E+06 O.OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO
- 0. OOE+OO
- 1. 34E+OO 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO.
- 3. 42E+08 2.25E+07 2.94E+08
- 6. 23E+03
- 0. OOE+OO O.OOE+OO 0.00E+OO G -LLI 1.88E+02
- 3. 95E+04
- 2. 19E+08 5.39E+05
- 1. 49E+06 1.96E+07 2.68E+06 6.60E+06
- 1. 95E+07 1.66E+08 2.16E+07
- 5. 71E+07 2.46E+07
- 1. 22E+08 4.93E+05 8.27E+04 2.25E+07
- 8. 33E- 08 6.87E+06 1.51E+03 1.08E+04
- 1. 21E+05 1.44E+09
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 52E+07 3.27E+07
- 1. 19E+07
- 8. 73E+05
- 1. 66E+07 9.95E+06
- 1. 57E+07
- 6. 04E+06
- 1. 93E+04
- 1. 35E+06
- 1. 13E+07 Al I nucl ides ( except H-3 and C-14) cal cul at ed per' CDCM equation 2. 3-24 H-3 cal cul at ed per CDCM equat i on 2. 3-28 C-14 cal cul at ed per ERS-LlvR- 001
Beaver Valley Power Station
Title:
ODCM: GASEOUS EFFLUENTS Pat hway = <?oat M I k Age Q-oup = I nf ant Nuclide 1
H-3 2
C 14 3
P-32 4
Q- - 51 5
Ml-54 6
Fe-59 7 Co-57 8 Co-58 9
Co-60 10 Zn-65 11 Se-75 12 Rb-86 13 Sr-89 14 Sr-90 15 Y-91 16 Zr-95 17 l\\b-95 18 l\\b-97 19 M:>- 99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-110m 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I - 131 30 I - 133 31 Cs-134 32 Cs-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone
- 0. OOE+OO
- 3. 87E+05
- 1. 63E+10
- 0. OOE+OO
- 0. OOE+OO
- 2. 17E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 4. 76E+08
- 0. OOE+OO O.OOE+OO
- 1. 21E+09
- 9. 86E+09
- 6. 94E+03 6.40E+02
- 5. 84E+04
- 3. 16E-12
- 0. OOE+OO
- 2. 81 E+OO
- 8. 47E+02
- 1. 60E+04
- 3. 30E+07
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 3. 80E+07 5.50E+07
- 2. 77E+08
- 3. 70E+06
- 3. 02E+09
- 2. 01E+08
- 4. 17E+09 2.45E+07
- 4. 14E+OO
- 4. 29E+03
- 1. 98E+05 ATTACHMENTJ Page 19 of 19 P&I ORGAN DOSE FACTORS Table 2.3-20 R VALUES FCR BEAVER VALLEY SI TE
( sq rret er-rrr em' yr per ua / sec)
Liver 2.86E+02
- 8. 27E+04 9.59E+08 O.OOE+OO 3.31E+06
- 3. 79E+07
- 7. 64E+05
- 2. 26E+06 7.20E+06
- 1. 63E+09
- 1. 15E+09
- 2. 25E+09 O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 1. 56E+02
- 2. 41 E+04 6.74E-13
- 2. 12E+07
- 5. 79E+OO
- 0. OOE+OO
- 0. OOE+OO
- 2. 41 E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 1. 26E+07
- 1. 89E+07
- 3. 27E+08
- 5. 39E+06 5.62E+09 5.92E+08
- 4. 89E+09
- 2. 45E+04
- 1. 63E+OO
- 2. 62E+03
- 8. 11 E+04 T.
Body
- 2. 86E+02 8.27E+04
- 6. 32E+08
- 1. 61E+04
- 7. 50E+05
- 1. 50E+07
- 1. 24E+06
- 5. 64E+06
- 1. 70E+07
- 7. 53E+08
- 4. 96E+08
- 1. 11 E+09
- 3. 46E+07
- 2. 51 E+09.
- 1. 85E+02
- 1. 11 E+02
- 1. 39E+04
- 2. 43E-13
- 4. 14E+06
- 7. 46E+01
- 2. 83E+02
- 2. OOE+03
- 1. 60E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 4. 59E+06
- 8. 47E+06
- 1. 44E+08
- 1. 58E+06
- 5. 68E+08 2.21E+08
- 3. 46E+08
- 1. 26E+06
- 4. 19E- 01
- 3. 08E+02
- 1. 11 E+04 Thyroid
- 2. 86E+02
- 8. 27E+04 O.OOE+OO
- 1. 05E+04
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 1. 10E+07
- 2. 11E+07
- 1. 07E+11
- 9. 80E+08
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO O.OOE+OO Procedure Number:
Unit:
1/2 Revision:
11 Kidney 2.86E+02 8.27E+04 O.OOE+OO 2.29E+03 7.33E+05 O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 7. 92E+08
- 1. 12E+09
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 1. 68E+02
- 1. 72E+04
- 5. 27E-13
- 3. 17E+07 6.23E+01
- 1. 76E+03
- 1. 90E+04 3.45E+07
- 0. OOE+OO O.OOE+OO O.OOE+OO 9.35E+07
- 1. 38E+08 3.82E+08
- 6. 34E+06
- 1. 45E+09
- 2. 36E+08 1.31E+09 5.83E+03 O.OOE+OO 8.07E+02 3.28E+04 l/2-0DC-2.02 Level Of Use:
General Skill Reference Page Number:
110 of 111 Lung
- 2. 86E+02 8.27E+04
- 0. OOE+OO
- 2. 04E+04,.
- 0. OOE+OO
- 1. 12E+07
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO 3.03E+OO
- 0. OOE+OO O.OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO O.OOE+OO
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO 5.93E+08
- 4. 82E+07 5.31E+08 1.51E+04
- 0. OOE+OO
- 0. OOE+OO
- 0. OOE+OO G -LLI 2.86E+02 8.27E+04 2.21E+08 4.69E+05
- 1. 21E+06
- 1. 81E+07 2.60E+06 5.64E+06
- 1. 71E+07
- 1. 38E+09
- 2. 15E+07
- 5. 77E+07 2.48E+07
- 1. 23E+08 4.98E+05
- 7. 77E+04
- 2. 03E+07 2.13E-07 6.99E+06
- 1. 68E+03
- 1. 03E+04
- 1. 22E+05 1.25E+09
- 0. OOE+OO O.OOE+OO O.OOE+OO
.1. 53E+07 3.28E+07
- 1. 17E+07
- 9. 12E+05
- 1. 53E+07 8.99E+06
- 1. 53E+07 6.03E+06
- 1. 92E+04
- 1. 35E+06
- 1. 14E+07 Al I nucl ides ( except H-3 and C-14) cal cul at ed per CDCM equation 2. 3-24 H-3 cal cul at ed per <DCM equat i on 2. 3-28 C 14 cal cul at ed per ERS-UvR- 001
SECTOR N
-NNE NE ENE E
WNW NW NNW 0.0 - 0.5 6.00E-10 6.66E-I0 1.03E-09 l.13E-09 l.35E-09 9.82E-10 2.76E-09 2.22E-09 3.00E-09 1.44E-08 l.89E-08 l.57E-09 3.78E-10 4.54E-10 4.52E-I0 3.40E-10 TABLE 2.3-21 PV-1/2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR
-2 (meters )
DISTANCES TO THE CONTROL LOCATIONS, IN MILES 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 8.60E-09 3.14E-09 l.76E-09 8.12E-I0 5.70E-I0 4.24E-I0 3.29E-I0 5.64E-09 1.98E-09 2.55E-09 l.33E-09 l.07E-09 6.75E-I0 5.23E-I0 1.57E-09 l.32E-09 3.62E-09 2.63E-09 1.64E-09 l.23E-09 6.13E-10 1.55E-09 3.69E-09 3.27E-09 2.3IE-09 l.29E-09 l.2IE-09 6.78E-I0 l.28E-08 4.09E-09 3.I2E-09 l.9IE-09 l.36E-09
-l.OlE-09 7.83E-10 7.85E-09 4.40E-09 2.46E-09 l.47E-09 1.03E-09 5.65E-10 5.05E-I0 6.4IE-09 3.52E-09 l.97E-09 l.18E-09 8.27E-10 5.68E-10 4.40E-10 4.66E-09 3.0lE-09 l.68E-09 1.02E-09 7.14E-10 4.25E-10 3.29E-10 4.81E-09 3.76E-09 2.lOE-09 l.36E-09 9.52E-10 5.12E-10 3.96E-IO 2.89E-09 7.83E-10 8.84E-10 5.70E-IO 4.00E-10 2.55E-10 l.98E-10 5.55E-09 l.55E-09 8.71E-10 2.6IE-10 3.94E-10 1.57E-IO 2.50E-10 6.63E-09 l.36E-09 l.04E-09 5.44E-10 2.39E-IO 3.84E-I0 2.98E-I0 2.95E-09 l.84E-09 l.03E-09 6.63E-10 4.66E-10 l.37E-IO 2.68E-10 4.13E-I0 3.09E-I0 4.7IE-10 7.35E-10 5.16E-10 l.93E-I0 1.lOE-10 4.09E-10 2.86E-10 l.18E-09 7.04E-IO 4.94E-10 3.37E-10 2.IOE-10 2.05E-09 l.63E-09 9.12E-10 5.86E-IO 4.13E-10 2.79E-IO 2.16E-10 4.0-4.5 2.63E-10 4.56E-I0 7.85E-10 6.72E-IO 4.15E-10 3.25E-IO 2.93E-10 2.19E-IO 2.68E-IO 1.84E-I0 2.54E-10 2.l 7E-IO l.12E-I0 l.12E-IO 2.09E-I0 l.73E-IO 4.5 - 5.0 2.15E-10 3.74E-10 6.42E-I0 3.89E-10 5.IOE-10 3.00E-10 2.43E-10 l.SOE-10 2.20E-10 1.5IE-10 2.08E-10 l.78E-10 l.75E-I0 l.80E-IO l.7IE-10 l.42E-IO
0
- l 0
~
TABLE 2.3-22 n ;
CV-1 AND CV-2 DEPOSITION PARAMETERS (D/Q) FOR
~
CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR
-2 00 td (meters )
n trJ 0
~
~
c:::
~
00
>-l trJ
~
DISTANCES TO THE CONTROL LOCATIONS, IN MILES z
>Tj
~
c:::
>Tj 0
r<
SECTOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 -4.5 4.5 - 5.0 c:::
i
~ -
00 N
4.46E-08 7.73E-09 3.24E-09 l.81E-09 1.0SE-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10
~
>-l
~
00 NNE 5.42E-08 9.39E-09 3.37E-09 l.89E-09 l.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 r<
~
trJ >
0 NE 7.32E-08 l.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 l.OOE-09 7.77E-10 5.69E-10 4.66E-10 00
~
trJ
~
ENE 7.77E-08 l.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 I.31E-09 l.OlE-09 6.58E-10 5.39E-10 0
>-l
~
~ ""C ~
r::/).
0~ 0 00 G ~
~
E 6.0SE-08 l.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10
~N
....... 0 0
ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 l.87E-10 0 >-ti z
~
z -..J SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-l0 4.12E-10 3.19E-l0 2.55E-10 2.09E-10
""C
>-l
~
~
SSE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 l.85E-10 l.52E-10
~
>-l s
3.67E-08 6.37E-09 2.26E-09 l.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-l0 l.96E-l0
~
C
~
00
(>
SSW 2.61E-08 4.52E-09 l.60E-09 8.97E-10 5.78E-l0 4.06E-10 3.02E-l0 2.34E-10 l.70E-10 l.39E-10 t-,-1, n*
0
-- ~:
(>
0 N
- p.
....... 0 C:
I
?.
SW 3.06E-08 5.30E-09 2.62E-09 l.47E-09 8.0lE-10 5.62E-10 4.18E-I0 3.24E-l0 2.35E-10 l.93E-10 V,
~
z WSW 4.60E-08 7.97E-09 3.34E-09 l.87E-09 l.20E-09 8.45E-10 5.87E-l0 4.55E-10 3.38E-10 2.77E-10
....... § p
~ C) ~ N ;r trJ I
('1) < o**
00
(>
z ~ 0 0
....... § I>>..., n w
6.49E-08 l.13E-08 4.72E-09 2.64E-09 l.19E-09 8.36E-10 6.22E-l0 4.82E-l0 3.85E-10 3.15E-10 I-' ~ -c
~
tvif en"'
WNW 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 l.55E-09 1.16E-09 8.96E-10 5.79E-l0 4.75E-10
~~ a~ 0 N
~
NW l.19E-07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.lOE-09 l.56E-09 1.21E-09 7.83E-10 6.4IE-10
~
~
('1)
NNW 5.22E-08 9.04E-09 3.79E-09 2.12E-09 l.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-l0 0
('1)
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
113 of 1 i 1 ATTACHMENT K Page 3 of7 11 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-23 VV-1 AND VV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRSNR OR> 150 HRS/QTR (meters-2)
Same as Table 2.3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
112 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
11 Page Number:
114 of 131 ATTACHMENT K Page 4 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-24 TV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRSNR OR> 150 HRS/QTR (meters*2)
Same as Table 2.3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT K Page 5 of7 11 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-25 CB-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR (meters-2)
Same as Table 2.3-22 115 of n 1 i
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
11 Page Number:
J J t, of 111 ATTACHMENTK Page 6 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-26 DV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRSNR OR>l50 HRS/QTR (meters-2)
Same as Table 2.3-22
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
112 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
117 of 111
.ATTACHMENTK Page 7 of7 11 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-27 WV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRSNR OR>ISO HRS/QTR
( l!leters-2)
Same as Table 2;3-22
. Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1 /2 General Skill Reference Revision:
Page Number:
11 11 8 of 1 11 ODCM: GASEOUS EFFLUENTS ATTACHMENTL Page 1 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-28 PV-1/2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRS/YR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters*2)
INDIVIDUAL RECEPTORS DOWNWIND*
SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN cow GOAT ANIMAL RESIDENCE N
.600 2.340
.572
.707 2.510 NNE
.673 3.220
.524 2.920 3.220 NE
.766 1.280
.660
.111
.660 1.200 ENE 1.010 5.080
.702 1.760 E
1.370 4.420
.401 1.290 1.290 4.420 ESE
.984 6.390 2.340 6.390 6.180 SE I 1.000 3.680
.466
.466 1.300 3.680 SSE 7.060 3.220
.423
.105 3.140 4.320 s
5.780 1.540 1.410 2.610 2.730 SSW 2.040 1.040
.578
.208 1.040 1.460 SW 1.610 1.120
.693
.979 1.120 WSW l.710 1.310
.370 1.190 1.310 w
.377
.659
.138
.518
.659 WNW
.424
.746
.497
.029
.746
.746 NW
.447
.425
.070
.488
.422 NNW
.340 1.840
.043
.545 1.92
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 119 nf 131 ATTACHMENT L Page 2 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-29 CV-1 AND CV-2 DEPOSTION PARAMETERS (D/Q} FOR CONTINUOUS RELEASES
>500 HRS/YR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters-2)
INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN cow GOAT ANIMAL RESIDENCE N
25.40 2.05
.693
.847 2.19 NNE 18.80 2.02
.459 1.850 2.11 NE 63.40 29.30
.455
.078
.455 30.40 ENE 65.90 8.92
.661 32.20 E
38.00 3.90
.382 1.020 1.020 22.70 ESE 17.10 3.56 1.380 3.560 3.56 SE 13.80 3.03
.350
.350 1.100 3.03 SSE 10.50 2.65
.317
.094 2.570 3.68 s
10.60 1.05
.934 1.860 1.95 SSW 5.59 1.26
.663
.266 1.260 4.42 SW 3.94 2.21 1.320 1.920 2.21 WSW 27.50 2.65
.596 2.380 2.65 w
31.60 1.23
.645
.960 1.23 WNW 39.10 2.23 1.490
.045 2.230 2.23 NW 70.60 15.00
.276 1.990 15.60 NNW 31.50 6.52
.068 1.090 9.91
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
1 l Page Number:
ATTACHMENT L Page 3 of7 120 of 111 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-30 VV-1 AND VV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRS/YR OR>150 HRS/QTRFOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(IE-9 meters*2)
Same as Table 2.3-29 J
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
l J__
l__Qf_J__3 l ATTACHMENT L Page 4 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-31 TV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRS/YR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters-2)
INDIVIDUAL RECEPTORS MEAT DOWNWIND SECTOR SITE BOUNDARY VEGETABLE GARDEN MILK cow MILK GOAT ANIMAL RESIDENCE N
NNE NE ENE E
WNW NW NNW 20.20 34.90 54.20 57.50 38.10 18.60 19.00 13.30 11.30 6.44 3.95
. 25.10 28.40 30.90 56.10 25.10 2.05 2.02 29.30 8.92 3.90 3.56 3.03 2.65 10.40 1.26 2.21 2.65 1.23 2.23 14.90 6.53
.455
.382
.351
.318
.934
.664
.597
.646 1.490
.693
.459
.078
.661 1.020 1.380
.351
.094
.266 1.320
.045
.276
.068
.847 1.850
.455 1.020 3.560 1.100 2.570 1.860 1.260 1.920 2.380
.961 2.230 1.980 1.100 2.190 2.110 30.400 32.200 22.700 3.560 3.030 3.690 1.950 4.430 2.210 2.650 1.230 2.230 15.500 9.920
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
11 Page Number:
}?') ofnl ATTACHMENT L Page 5 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-32 CB-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRS/YR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(IE-9 meters"2)
Same as Table 2.3-31 J
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 1?~ ofl31 ATTACHMENTL Page 6 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-33 DV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(IE-9 meters*2)
Same as Table 2.3-29
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
11 Page Number:
l')LI. of 111 ATTACHMENT L Page 7 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-34 WV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
>500 HRSNR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters-2)
Same as Table 2.3-29
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
11 125 of 131 ATTACHMENTM Page 1 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-35 CV-1 AND CV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES s500 HRS/YR OR sl50 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(sec/m3)
INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*
BOUNDARY GARDEN cow GOAT ANIMAL RESIDENCE N
8.21E-5 8.38E-6 3.72E-6 4.34E-6 8.82E-6 NNE 3.04E-5 4.71E-6 1.40E-6 4.38E-6 4.87E-6 NE 4.59E-5 2.21E-5 6.0SE-7 l.38E-7 6.0SE-7 2.28E-5 ENE 3.72E-5 5.25E-6 5.66E-7 l.88E-5 E
2.93E-5 3.79E-6 5.lSE-7 l.17E-6 1.l 7E-6
- l.78E-5 ESE 2.47E-5 5.61E-6 2.34E-6 5.61E-6 5.61E-6 SE 2.14E-5 5.00E-6 8.13E-7 8.13E-7 2.03E-6 5.00E-6 SSE 2.21E-5 6.31E-6 l.llE-6 3.92E-7 6.13E-6 8.49E-6 s
2.lSE-5 3.03E-6 2.76E-6 4.93E-6 5.14E-6 SSW 2.18E-5 6.58E-6 3.81E-6 l.82E-6 6.58E-6 l.78E-5 SW 1.82E-5 l.03E-5 6.67E-6 9.12E-6 l.03E-5 WSW l.09E-4 l.29E-5 4.IOE-6 l.19E-5 1.29E-5 w
1.49E-4 l.05E-5 6.55E-6 8.77E-6 l.OSE-5 WNW l.91E-4 l.72E-5 l.28E-5 1.23E-6 l.72E-5 l.72E-5 NW 3.08E-4 6.13E-5 3.80E-6 1.36E-5 6.36E-5 NNW l.80E-4 3.54E-5 l.35E-6 9.27E-6 5.29E-5
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
11 Page Number:
ATTACHMENT M Page 2 of 3 1 ?6 of 131 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-36 VV-1 AND VV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES s500 HRS/YR OR sl50 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(sec/m3)
INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*
BOUNDARY GARDEN cow GOAT ANIMAL N
9.75E-5 1.00E-5 4.21E-6 4.95E-6 NNE 3.78E-5 5.llE-6 1.43E-6 4.72E-6 NE 6.13E-5 2.70E-5 6.20E-7 1.40E-7 6.20E-7 ENE 4,83E-5 5.58E-6 5.71E-7 E
3.66E-5 3.99E-6 5.25E-7 1.19E-6 1.19E-6 ESE 2.99E-5 6.13E-6 2.43E-6 6.13E-6 SE 2.55E-5 5.29E-6 8.24E-7 8.24E-7 2.13E-6 SSE 2.65E-5 6.72E-6 1.12E-6 3.95E-7 6.53E-6 s
2.52E-5 3.14E-6 2.83E-6 5.29E-6 SSW 2.60E-5 7.34E-6 4.15E-6 l.92E-6 7.34E-6 SW 2.13E-5 1.18E-5 7.41E-6 l.04E-5 WSW l.34E-4 1.SlE-5 4.46E-6 1.38E-5 w
1.77E-4 1.25E-5 7.40E-6 l.02E-5 WNW 2.33E-4 2.07E-5 1.49E-5 1.30E-6 2.07E-5 NW 3.32E-4 8.57E-5 4.24E-6 1.64E-5 NNW l.90E-4 4.69E-5 1.45E-6 l.09E-5
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 RESIDENCE l.06E-5 5.30E-6 2.81E-5 2.24E-5 2.lOE-5 6.13E-6 5.29E-6 9.22E-6 5.53E-6 2.09E-5 1.18E-5 1.51E-5 1.25E-5 2.07E-5 8.85E-5 6.75E-5
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
I /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Nwnber:
11 127 of B 1 ATTACHMENT M Page 3 of3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-37 PV-1/2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES s500 HRS/YR OR s150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(sec/m3)
INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*
BOUNDARY GARDEN cow GOAT ANIMAL N
3.09E-9 3.30E-6 1.13E-6 1.34E-6 NNE 2.85E-9 2.68E-6 6.52E-7 2.47E-6 NE 2.02E-10 7.42E-9 5.44E-7 1.24E-7 5.44E-7 ENE 1.02E-9 3.21E-6 6.29E-7 E
2.15E-9 2.91E-6 4.96E-7 1.14E-6 1.14E-6 ESE 6.90E-9 4.97E-6 1.95E-6 4.97E-6 SE 2.91E-6 3.52E-6 6.02E-7 6.02E-7 l.43E-6 SSE 4.91E-6 3.56E-6 6.53E-7 2.18E-7 3.47E-6 s
2.41E-6 l.78E-6 1.65E-6 2.84E-6 SSW 4.83E-6 2.52E-6 l.SOE-6 6.60E-7 2.52E-6 SW 4.82E-6 2.75E-6 1.78E-6 2.44E-6 WSW 5.77E-7 2.81E-6 8.79E-7 2.57E-6 w
2.88E-9 l.68E-6 4.89E-7 l.37E-6 WNW 3.40E-9 1.61E-6 1.13E-6 l.lOE-7 1.61E-6 NW l.34E-9 3.3 lE-8 2.03E-7 1.07E-6 NNW l.52E-9 3.73E-6 l.73E-7 l.31E-6
- Measured relevant to BV-1 natural draft cooling tower Period of Record: 1976 - 1980 RESIDENCE 3.36E-6 2.68E-6 5.SIE-9 l.67E-9 2.91E-6 4.81E-6 3.52E-6 4.71E-6 2.96E-6 3.96:E-6 2.75E-6 2.81E-6 l.68E-6 l.61E-6 3.lOE-8 3.81E-6
0 a:
0
~
n ?;
§2 TABLE 2.3-38 CZl to trJ 0
(D PV-1/2 DISPERSION PARAMETERS (X/Q) FOR to c
~
BATCH RELEASES ~ 500 HRS/YR OR~ 150 HRS/QTR CZl
>-J trJ (D
(sec/m3) n
>Tj
~
>Tj
- c:
L"
~
~
~ -
L" DISTANCES TO THE CONTROL LOCATIONS, IN MILES
~
>-J
~
CZl CZl
~
SECTOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0- 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 trJ 0
0
~
CZl N
2.75E-15 l.07E-5 4.lOE-6 2.61E-6 1.51E-6 1.13E-6 8.84E-7 7.13E-7 5.93E-7 5.06E-7
'"d (D
trJ
>-J
~
NNE 5.90E-17 5.39E-6 2.83E-6 2.19E-6 l.36E-6 l.13E-6 8.05E-7 6.51E-7 5.64E-7 4.81E-7
~ '"d ~
[fl NE 4.45E-16 l.67E-8 7.39E-8 2.28E-6 l.72E-6 l.19E-6 9.28E-7 6.76E-7 7.34E-7 5.32E-7 CZl p)
.-+-
ENE 1.92E-15 8.87E-8 2.60E-6 2.21E-6 1.66E-6 l.13E-6 9.25E-7 7.23E-7 6.06E-7 3.82E-7 0~ i
~
P~
~-
0 E
l.84E-15 5.lOE-6 2.77E-6 2.23E-6 1.44E-6 l.12E-6 8.74E-7 6.92E-7 5.llE-7 4.82E-7
>-J trJ
~
s l.22E-7 4.12E-6 3.97E-6 2.34E-6 1.59E-6 l.17E-6 7.75E-7 6.24E-7 4.74E-7 4.00E-7 CZl SSW l.75E-5 6.22E-6 2.84E-6 2.18E-6 l.48E-6 l.08E-6 7.83E-7 6.31E-7 5.62E-7 4.77E-7 0
C:
?
9.1 lE-6 I
(>
SW 2.08E-5 3.47E-6 2.19E-6 1.25E-6 1.1 IE-6 8.19E-7 7.17E-7 6.89E-7 5.85E-7 V,
< ~ ~-
0
~;:
(>
9.35E-6 N
WSW 8.56E-8 3.16E-6 2.29E-6 l.46E-6 l.OIE-6 9.06E-7 7.52E-7 5.99E-7 5.07E-7
~
I-< ~
C:
L" z
trJ
....... a w
5.44E-17 4.52E-6 4.21E-6 2.49E-6 l.69E-6 l.25E-6 4.86E-7 7.68E-7 5.80E-7 5.48E-7 CZl
- ,ti QI
- NC" I
!!l WNW 9.25E-18 l.44E-8 5.66E-8 l.92E-6 1.59E-6 l.17E-6 7.75E-7 4.6IE-7 5.28E-7 4.89E-7
~ (1) < o**
- i g, NW 2.6IE-16 1.98E-8 8.37E-8 2.24E-6 1.46E-6 l.08E-6 8.09E-7 6.12E-7 5.42E-7 4.60E-7 z ~ ~ 0 I-< E:
n NNW l.9IE-15 3.9IE-6 3.66E-6 2.15E-6 l.40E-6 l.08E-6 8.03E-7 6.48E-7 5.37E-7 4.56E-7 N::, E..c:::
I k)o if Cl.)"' N
~
- 1 §~ 0 N I-<
~
~
~
(1)
- i
(")
(1)
,i Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
ATTACHMENT 0 Page 1 of 1 GASEOUS RADWASTE SYSTEM FIGURE 2,4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM
.r~-------------
u !'ROIi UHJT Z GASEOUS NAST£ SYSTDI (SINILAR TO UKII 1l PID'ILtDIS UNlf 1 GAS COIIPSIISSOI jsum TAIIX !
!111:tar JANI I UNIT 2 GAS COIIPIIISSOI SUIQE TAIBI I IDECAV fANK I r**********
I 1118 jux:.v 111111 !
j>>ICllV TAIi< j A
.. --..___~----.1>'<1~
DIGl1SJfJD SIIDP GAS DIW!IOII All t,
OICVGDI *IIIILVID t,
COIIDDISOI Al R LIECIOI t, IIAl>IAIIOII NOlfllOI ftlllGE
- COfffAIIIIDff U!IQJUJI FUIIPS t>
Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level OfUse:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
ATTACHMENT P Page 1 of 1 BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS FIGURE 2,4-2 BV-1 ANO 2 GASEOUS EFFLUENT RELEASE POirn'S D
CJ
-z-- Ohio (D
..,.. u Point & Dtteript Ion iver D
tlevatlon
- 1. U,lt 1:
Ventll,tfon Vent 7'9 f"t
- 24 *t*ra
- 2. Uollt h COr\\t*IMltftt / SLCSIS Vent 1S4 fftt
- 47 Pttcra
- 3. unit 1'2: l'roetu Ytt1t s2s Ifft
- 16/J *ten
- 4. Unit 2:
Vtntll*tlOII Vfflt 8S feet
- 26 *t*r*
- 5. Unit 2:
cont1llftflt / su:as Vent 154 fNt
- 47 ***rs
- 6. Unit 2:
condtMatl Pollllllt111 lulldlng Vtftt eo fNt
- 24 *Htrl
- 7. Unlr 2:
waste c.1 Storase V.ult Vent eo '"' = 2.4 acter,
- e. '-" 2:
Oecont*IMtlon lulldlnsr Vent eo feet
- 2' *tffl
- 9, U...lt 2:
turbine aulldfng vent 109 feet
- n acter,
~te: TM l!tl.. k Point f,hown for tllt lA'llt z lUl'blnt lulldl~ Verit II 1 rcprr-atnt.clw uh~t point for tht 10 roof ellheun outlets.
B a
ii,.\\
lo, Beaver Valley Power Station Procedure Number:
l/2-0DC-2.02
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:
31__of__J_3 CD CD
....* \\
.. *~
- =.
ATTACHMENT Q Page 1 of 1 SITE BOUNDARY FOR GASEOUS EFFLUENTS Figure 5-1
~
en Wllex>
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- E....
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~
L.. g_
- 0)
C:
- 5.
C.
- E I
I I I,*
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.g
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0 0
m =
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~
=~
~
OU I
.u.u 1:1.S::
a, a, I
GJO~
.u.c:
~....
0
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OO.&Jrn I
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