Text

ODCM: Gaseous Effluents
	ML21127A156
Person / Time
Site:	Beaver Valley
Issue date:	07/17/2019
From:	; Energy Harbor Nuclear Corp
To:	; Office of Nuclear Reactor Regulation
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ML21127A168	List: L-21-135, ODCM: Liquid Effluents; ML21127A144; ML21127A148; ML21127A149; ML21127A151; ML21127A155; ML21127A156; ML21127A158; ML21127A159; ML21127A162; ML21127A165;
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RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-0DC-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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11

?. of 131 TABLE OF CONTENTS 1.0 PURPOSE......................................................................................................................................... 4 2.0 SCOPE.............................................................................................................................................. 4

3.0 REFERENCES

AND COMMITMENTS......................................................................................... 4 3.1 ~*-*-----------*-----------------4 32 011n1ritmeuts --*------------------------7 4.0 RECORDS AND FORMS................................................................................................................ 7 4.1 Rf:cx:tm.----*--*----*---*--------------7 42 Fcnm _______________________________ 7 5.0 PRECAUTIONS AND LIMITATIONS.......................................................................................... 7 5.1 Prea,n:m ____ *------------------*-*-*-----*7 52 Jimitatiaos_,_*---*----------------~------------*8 6.0 ACCEPTANCE CRI'TERIA............................................................................................................. 9 7.0 PREREQUISITES............................................................................................................................ 9 8.0 PROCEDURE................................................................................................................................. 10 8.1 AlannSapools.__. __. _____ *------------*--------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 Alarm Setpoint Determination.................................................. 29 8.2 ~

W:tlh 10 ~20DoseRateumits(ODCMCONIROL3.112.1)---*------35 8.2.1 Dose Rate Due To Noble Gases.......................................................................... 35 8.2.2 Dose Rate Due To Radioiodines And Particulates.............................................. 43 83 ~

W:tlh 10GR.50Dosel.imits(OOCMOONTROI.S 3.1122Am3.1123)(Gaserus) _____ 46 8.3.1 Dose Due To Noble Gases................................................................................... 47 8.3.2 Dose Due To Radioiodines And Particulates...................................................... 54 8.4 Gmeoos~S}fflID.---------------------*---------*70 8.4.l 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 ATTACHMENT D ATTACHMENT E ATTACHMENT F ATTACHMENT G ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENT K ATTACHMENT L ATTACIIMENT M ATTACIIMENTN ATTACHMENT 0 ATTACHMENTP ATTACHMENT Q 11 3 nf 131 TABLE OF CONTENTS GASEOUS SOURCE TERM.............................................................................. 73 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES................ 75 DELETED............................................................................................................ 77 RADIONUCLIDE~...................................................................................... 78 DISTANCES TO RELEASE POINTS................................................................ 80 0-5 MII.E DISPERSION PARAMETERS.......................................................... 81 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS........................ 88 ORGAN DOSE P ARAlvfETERS........................................................................ 90 MODES OF GASEOUS RELEASE................................................................... 91 P&I ORGAN DOSE FACTORS......................................................................... 92 CONTINUOUS RELEASE DEPOSffiON PARAMETERS (0-5 MILES)..... 111 CONTINUOUS RELEASE DEPOSffiON PARAMETERS (SPECIAL DISTANCES).................................................................................................... 118 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES).................................................................................................... 125 BATCH RELEASE DISPERSION PARAMETERS (0 - 5 MILES)................ 128 GASEOUS RADWASTE SYSTEM................................................................. 129 BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POJNTS..................... 130 SITE BOUNDARY FOR GASEOUS EFFLUENTS........................................ 131

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4 of 131 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 Specifications [TS] 5.5.2.

1.1.1 Gaseous effluent monitor alarm setpoints [TS] 5.5.2.a 1.1.2 Gaseous effluent dose rate calculations [TS] 5.5.2.g 1.1.3 Gaseous effluent dose calculations [TS] 5.5.2.g, [TS] 5.5.2.h, [TS] 5.5.2.i 1.1.4 Gaseous Radwaste Treatment System [TS] 5.5.2.f 1.1.5 Site Boundary used for gaseous effluents 2.0 SCOPE 2.1 This procedure is applicable to gaseous effluents at Beaver Valley Power Station.

3.0 REFERENCES

AND COMMITMENTS 3.1 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-IIlIM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification Letter NDlSHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, AppendixB Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps

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5 nf 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 ORMS Isotopic Efficiencies Calculation Package No. ERS-IIllM-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) 1 3.1.3.3 NUREG-0324; XOQDOQ Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations, September 1977 3.1.3.4 NUREG-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents form PWR's Revision 0.

3.1.3.5 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Release of Reactor Eflluents 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 of Implementing 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 nf n1 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-ODC-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 IA-302) to License No.

DPR-66. This amendment to the Unit 1 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-ODC-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, Selenium-75 (Se-75) discharge via Ul/U2 Process Vent. CA-02 revises ODCM procedure l/2-0DC-2.02 to include dose factors for Se-75.

3.1.3.22 Technical Evaluation Package ERS-LMR.-12-001, ODCM Pi't and R values for Carbon-14.

3.1.3.23 Notification 600727275 and CR #2012-17177, Revise l/2-ODC-2.02, Gaseous Effluents, with the Rvalues for Sb-126.

3.1.3.24 Notification 600737534 Item #4, Revise ODCM for Carbon-14.

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11 7 nf 1 '.\\ 1 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. ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for 1/2-ENV-05.06 3.1.3.27 Calculation Package No. ERS-ATL-89-014; Verification/Validation ofODCM 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 3.1.3.31 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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R of 131 5.2 Limitations 5.2.l Offsite Dose Calculation Manual (ODCM) controls applicable to dose rate apply to the site. The site dose rate is calculated by l'!umming 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 BY -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 radwaste 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.l 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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QnfBl 5.2.6.2 52.6.3 5.2.6.4 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.U.3) 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 O:ffsite Dose Calculation Manual.

5.2.7.1 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 of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix Ito 10 CFR 50, and not adversely impact the accmacy or reliability of effluent dose or alarm setpoint calculation.(3.1.32 )

6.1.1 Changes to this procedure shall be prepared in accordance with 1/2-ADM-0100, PROCEDURE WRITER'S GUIDE (3.1 3.s) and l/2-ADM-1640, CONTROL OF TIIE OFFSITE DOSE CALCULATION MANlJAL_{3.I.3.7) 6.1.2 Changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001, PROCEDURE REVIEW AND APPROVAL (3.13.9> and l/2-ADM-1640.

(3.1.3.7) 7.0 PREREQUISITES 7.1 None.

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10 nf 131 8.0 PROCEDURE 8.1 Alarm Setpoints 8.1.1 BV-1 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

~ 500 mrem/yr to the total body and to~ 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 of 131 Monitor Setpoint Specifications B~ed On Fraction Of Site Limit UNIT RELEASE POINT MONITORNO.

FRACTION OF SITE LIMITING DOSE RA TE (VV-1) Unit 1, Auxiliary Building Vent Pri.: RM-lVS-109 LRNG or Alt: RM-lVS-lOlB (CV-1) Unit 1, Rx Containment/SLCRS Vent Upper Alarm 60% (IIlGH) 60% (IIlGH-IIlGH)

Pri.: RM-lVS-110 LRNG or 60% (IIlGH)

Alt: RM-1VS-107B 60% (IIlGH-IIlGH)

(PV-1/2), Unit 1/2, Gaseous Waste/Process Vent Pri.: RM-1GW-108B or 60% (IIlGH-IIlGH)

Alt: RM-lGW-109 LRNG 60% (IIlGH)

(CV-2), Unit 2, SLCRS Filtered Pathway 2HVS-RQ 109E 60% (IIlGH)

(VV-2), Unit 2, SLCRS Unfiltered Pathway 2HVS-RQ101B 60% (IIlGH)

(WV-2), Unit 2, Waste Gas Storage Vault Vent 2RMQ-RQ303B 60% (IIlGH)

(DV-2), Unit 2, Decontamination Building Vent 2RMQ-RQ301B 60% (IIlGH)

Lower Alarm 30%(ALERT) 30%(ALERT) 30%(ALERT) 30% (IIlGH) 30% (IIlGH) 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) % of the site dose rate limit when any monitor is indicating an Upper Alarm and any other monitor is indicating a Lower Alarm.

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12 of 131 8.1.1.l 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:

BVl ALARM SETPOINTS FOR GROUND RELEASES NET ABOVE BACKGROUND (P)PRIMARY*MONITOR (A) ALTERNATE MONITOR

Continuous Release Via The BV-(P) RM-lVS-109 LRNG-<1>

1 Auxiliary Building Vent (VV-1)

(A) RM-1VS-101B

Batch Release Of Containment (P) RM-lVS-109 LRNG<1>

Purge Via The BV-1 Auxiliary Building Vent (VV-1)

(A) RM-1VS-101B

Continuous Release Via The BV-(P) RM-1VS-110 LRNG<1>

1 Rx Containment/SLCRS Vent (CV-1)

(A) RM-1VS-107B (P) RM-lVS-110 LRNG<1>

(A) RM-1VS-107B CR 625 cps 4080 cpm 6.36 cps 1490 cpm 13.9 cps 6580 cpm 27.4 cps 13,000 DV 2640

µCi/sec 1050

µCi/sec 3790

µCi/sec 1140

µCi/sec 6()0/4 30%

SITE SITE LIMIT LIMIT UPPER LOWER ALARM ALARM

$ 1580

5. 792

µCi/sec

$2450 5.1220 cpm cpm

$ 633

5. 316

µCi/sec

5. 2620

5. 1310 cpm cpm

5. 2270 5.1140

µCi/sec

$ 3950

5. 1970 cpm cpm

5. 682

5. 341

µCi/sec

$7790

5. 3890

Batch Release Of Containment Purge Via The BV-1 Rx Containment/SLCRS Vent (CV-1) cpm cpm cpm

IF the primary monitor is out of service, TiffiN 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, IDGH, and HIGH-HIGH. The HIGH-HIGH setooint will be used to swap from the low nllll!e monitor to the hiim ranj,te 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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B nf 131 Discharge flow rate of 62,000 cfm for a VV-1 Continuous Release.

Discharge flow rate of92,000 cfm for a VV-1 Batch Release of Containment Purge.

This is comprised of30,000 cfm from the containment purge plus 62,000 cfm for VV-1.

Discharge flow rate of 49,300 cfm for a CV-1 Continuous Release.

Discharge flow rate of 56,800 cfm for a CV-1 Batch Release of Containment Purge.

This is comprised of7,500 cfm 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-1.

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 Radionuclldes 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:

S.

~

1=

~i

[2.1(1)-1]

where:

A1 = 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 nf 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

[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.

=

l.03E-4 sec/m3 for continuous releases.

(X/q)w

=

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 Ki Si of effluents released via CV-1 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.

=

The highest calculated short term relative concentration of effluents released via CV~l 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.

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/u.Ci/m3) from ATTACHMENT G Table 2.2-11.

=

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 BV-1 Maximum Acceptable Release Rate (Skin Exposure)

Qt was also determined based upon the skin exposure limit by:

Qt-3000

- (X/Q) I (Li + l.lMJ S1 i

where:

15 nf 131

[2.1(1)-3]

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 8.1.1.1.2.

BV-1 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 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 (Individual Radionuclide)

The maximum acceptable radioactivity concentration (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:

Q = 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 ft'/cc).

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16 nf 111 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 Mirion Monitors) above background attnbuted to the noble gas radionuclide.

CR was determined by:

[2.1(1)-6)]

where:

Bi = The detection efficiency of the monitor for noble gas radionuclide "i"

( cpm/uCi/cc for Victoreen or cps/uCi/cc for Mirion) from ATTACHMENT B Table 2.1-2a.

BV-1 Monitor Setpofnts The monitor alarm setpoints above background were determined as follows:

The Victoreen monitor IIlGH-HIGH Alarm Setpoint above background (ncpm) was determined by:

HHSP = 0.60 x CR

[2.1(1)-7]

The Victoreen monitor IIlGH Alarm Setpoint above background (ncpm) was determined by:

HSP = 0.30 x CR I [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 Mirion monitor HIGH Alarm Setpoint above background (uCi/sec) was determined by:

HSP = 0.60 x Qt

[2.1(1)-9]

The Mirion monitor ALERT Alarm Setpoint above background (uCi/sec) was determined by:

ASP = 0.30 x Qt

[2.1(1)-10]

NOTE: Use the lower of the Qt values obtained in Section 8.1.1.1.2 and 8.1.1.1.3.

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17 of 131 8.1.1.2 8.1.1.2.1 11 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 associated 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 Purge 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 (cfm) during purging based upon the whole body exposure limit is calculated by:

1.06 ST f = (X/q) t Kt Ct

[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.l.6)

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1 R nf'l ~ 1 (X/q}yy = 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 2.3-37.

= 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.

C1

= 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) t (Lt + 1.1Mt) Ct

[2.1(1)-18]

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)

L

= 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.

(X/q) = Same as above.

\\.

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1Q of Bl 8.1.1.2.2 The flow rate (f) is determined by selecting the smaller of the calculated (t) values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate ( cfm) must be maintained at or below this calculated (t) 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 backgr01md (ncpm) attnbuted to noble gas radionuclides is determined by:

f ~ Ct Et IIBSP =

F' where:

[2.1(1)-19]

f

= The maximum acceptable gaseous discharge flow rate ( c:fm) 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-I C1

= 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.

Bi

= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.l-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 BY-2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determinations.

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?O nf 131 8.12.1 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 BACK.GROUND (unless otherwise soecified) 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

~ 1.81E-4 ~ 9.04E-5 SLCRS Unfiltered Pathway (VV-2)

Batch Release Of Containment Purge 2HVS-RQ 101B 2020 7.39E-5

~ 4.43E-5 ~2.22E-5 Via The BV-2 SLCRS Unfiltered Pathway (VV-2)

Continuous Release Via The BV-2 2HVS-RQ 109B 4320 2940

~ 1770

~ 883 SLCRS Filtered Pathway (CV-2)

µCi/sec

µCi/sec Batch Release Of Containment Purge 2HVS-RQ109B 16,400 1130

~676

~ 338 Via The BV-2 SLCRS Filtered Pathway

µCi/sec

µCi/sec (CV-2)

Continuous Release Via The BV-2 2RMQ-RQ301B 56,600 3.lSE-3

~ 1.89E-3 ~ 9.44E-4 Decontamination Building Vent (DV-2)

Continuous Release Via The BV-2 2RMQ-RQ303B 912,000 2.58E-2

~ 1.55E-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.

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21 nf] 31 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 of23,700 cfm for a VV-2 Continuous Release.

Discharge flow rate of53,700 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 of7,500 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 of BV-2 Containment Purge via CV-2.

Continuous release via DV-2.

Continuous release via WV-2.

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?? nf 111 8.1.2.1.1 8.1.2.1.2 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 eflluent 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 2.1-1 b. 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) tKt St l

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.

= l.03E-4 sec/m3 for continuous releases.

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?.-:\\ of n1 8.1.2.1.3 11 (X/q)w = 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 ATTACHMENT F 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:

Qt=

3000 (X/Q) t (Lt + 1.1Mt) St

[2.1(2)-3]

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?A. nfBl 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 Qt values obtained in Section 8.1.2.1.2 and 8.1.2.1.3.

BV-2 Maximum Acceptable Concentrations (Individual 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:

Q = 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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?'inf 131 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:

[2.1(2)-6)]

where:

Bi

= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.l-2b.

8.1.2.1.7 BV-2 Monitor Setpolnq 8.1.2.2 The monitor alarm setpoints above background were determined as follows:

The monitor IIlGH Alarm Setpoint above background (uCi/cc) was determined by:

0.60 xCR HSP= Et ave

[2.1(2)-7]

where; Bi ave

= 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=

Et ave

[2.1(2)-8]

BV-2 Setpolnt Determination Based On Analysis Prior To Release for VV-2 and CV-2 Ground Rele&1e1 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 IIlGH 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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?ll nf 131 8.1.2.2.1 BV-2 Maxim.nm 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 (f) from VV-2 or CV-2 ( cfm) during purging based upon the whole body exposure limit is calculated by:

1.06 ST f = (X/q) t Kt Ct

[2.1(2)-17]

where:

1.06

= 500 mrem/yrx 2.12E-3 500 mrem/yr = dose rate limit, whole body exposure 2.12E-3

= unit conversion factor

= (60 sec/minx 3.53E-5 ft'/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 from noble gas radionuclide "i" (mrem/year/uCi/m3) from ATTACHMENT G Table 2.2-11.

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27 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.

The flow rate (f) is also determined based upon the skin exposure limit as follows:

6.36 ST f=--------

(X/q) 'o/ (Lt + 1.lMt) Ct

[2.1(2)-18]

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)

Li

= The skin dose factor due to beta emissions froin 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 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 ( cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.

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8.1.2.2.2 11

?~ of 131 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:

[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 forVV-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.

Bi

=

The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2. l-2b.

Bi 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 Bi 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 IITGH 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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?O nf'Bl 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 Setµoint 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 (IDISP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are shown in the following Table:

BV-1/2 ALARM SETPOINTS FOR GROUND RELEASES

Continuous Release (P) PRIMARY* MONITOR (A) ALTERNATE MONITOR (P)RM-1GW-108B (A)RM-lGW-109 LRNGC1>

Batch Release OfBV-1 Decay (P)RM-1GW-108B Tanks or BV-2 Storage Tanks (A)RM-lGW-109 LRNG<1>

CR 3.49E7 ncpm ABOVE BACK.GROUND (un1ess otherwise soecified) 60%

30%

SITE SITE LIMIT LIMIT UPPER LOWER DV ALARM ALARM

~ 3.60E5

~ 1.20E5

~m

~m 1.07E5 l.09E6

~ 6.56E5

~ 3.28E5 cps

µCi/sec

µCi/sec 3.93E5

~ 2.36E5

~ 1.18E5 cpm cpm cpm 3.54E4 2.25E5

~ 1.35E5

~ 6.75E4 cps

µCi/sec

IE 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, IIlGH, and IIlGH-IIlGH. The IIlGH-IIlGH setnoint will be used to swap from the low l'lllli!e monitor to the hi!!h raru!e monitor.

The setpoints were determined using a calculated mix from the UFSAR and discharge flow rate of 1450 cfm 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 or BV-2 Containment Purge via this release point, the alarm setpoint shall be calculated in accordance with Section 8.1.3.2.

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

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-:to nf 111 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 eflluent comprised by noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was calculated by:

S--~

i-t At where:

[2.1-9]

At

= 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 (Qi) based upon the whole body exposure limit was determined by:

500 Qt= t Vi St where:

[2.1.10]

V1 = 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.

S1 = From equation [2.1-9]

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11 of 111 8.1.3.1.3 8.1.3.1.4 8.1.3.1.5 BV-1/2 Maximum Acceptable Release Rate {Skin Exposure)

Qt was also determined based upon the skin exposure limit as follows:

3000 Qt=_Y. ____

T [Li(X/Q)pv + 1.1BtJSt

[2.1-11]

where:

L

= 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.

= 2.31E-6 sec/m3 (0.5 - 1.0 miles)

(X/q)pv = 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.

= 1.07E-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 Marlmum Acceptable Release Rate (Individual Radionuclide)

The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Q1) for each individual noble gas radionuclide in the gaseous effluent was determined by:

[2.1-12]

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 Maximum Acceptable Concentrations (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (C1) for each individual noble gas radionuclide in the gaseous effluent was determined by:

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32 nf 131 8.1.3.1.6 8.1.3.1.7 Q = 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 Mirion Monitors) above background attnbuted to the noble gas radionuclide.

(CR) was determined by:

[2.1-14]

where:

Bi

= The detection efficiency of the monitor for noble gas radionuclide "i"

( cpm/uCi/cc for Victoreen or cps/uCi/cc for Mirion) from ATTACHMENT B Table 2.1-2a and 2.l-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 back.ground (ncpm) was determined by:

HSP = 0.30 x CR

[2.1-16]

The Mirion monitor HIGH Alarm Setpoint above background (uCi/sec) was determined by:

HSP = 0.60 x Qt

[2.1-17]

The Mirion monitor ALERT Alarm Setpoint above background (uCi/sec) was determined by:

ASP = 0.30 x Qt

[2.1-18]

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33nf131 8.1.3.2 8.1.3.2.1 NOTE: Use the lower of the Qi values obtained in Section 8.1.3.12 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 flextoility. 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-108B) or alternate (RM-lGW-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 of BV-1 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:

1.06 S f= t Vt Ct

[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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-:t.d. of 111 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= t [Lt (X/Q)pv + 1.1Bt] Ct

[2.1-22]

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 ft'/cc)

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 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.

=

2.31E-6 sec/m3 (X/q)pv

=

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.

=

1.07E-5 sec/m3 B1

=

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 f values based on the whole body exposure limit and based on the skin exposure limit shown above. The actual discharge flow rate (cfm) must be maintained at or below this (f) value.

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~'i of131 8.1.3.2.2 where:

BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:

The calculated monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attnbuted to the noble gas radionuclides is determined by:

ft Ct Et HHSP=

p'

[2.1-23]

f

= The maximum acceptable gaseous discharge flow rate ( c:fm) determined in Section 8.1.3.2.1.

F'

= The maximum actual or design effluent flow rate ( cfm) at the point of release.

= 1450 cfm 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.

Bi

= The detection efficiency of the respective monitor (RM-1GW-108B) or (RM-lGW-109 LRNG) for noble gas radionuclide "i" (cpm/uCi/cc) from-ATTACHMENT B Table 2.l-2a and 2.1-2b.

When a HIGH-HIGH Alarm Setpoint has been calculated according to this section the monitor HIGH Alarm setpoint above backgrmmd (ncpm) is determined by:

HSP = HHSP x 0.5

[2.1-24]

82 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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16 nfBl effluents are the total of BV-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.l3.I) the following equations are used to show compliance with ODCM CONTROL 3.11.2.1.a.

[2.2-1]

L ((Li(X/Q)5 + 1.1Bt] Qts + [Lt + 1,1Mt] (X/Q),, Qw] $; 3000 mrem/yr [2.2-2]

t where:

Ki Li M1 Vi Bi

=

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", mrem/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.

1.1

=

The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad.

Qis

=

The release rate of noble gas radionuclide "i" in gaseous effluents from free-standing stack, uCi/sec.

Q1v

=

The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCi/sec.

(XI Q ). = 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 ATTACHMENT P 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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17 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.

The 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 3.11.2.1.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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11 38nf131 8.2.1.1 Total Body Dose Rate (All Release Points)

500 mrem/yr

[2.2-3]

8.2.1.2 Skin Dose Rate {All Release Points)

(X/Q)vv Qiwi +

(X/Q)cv Qiev2 + (X/Q)vv QivPi + (X/Q)tr, QiM +

(X/Q)cb Qicb2 + (X/Q)dv

[2.2-4]

where:

Q.

= Release rate of radionuclide "i" from the PV-1/2, uCi/sec.

1 pv Q

= Release rate of radionuclide "i" from CV-1, uCi/sec.

1cvl Q.

= Release rate of radionuclide "i" from CV-2, uCi/sec.

1 cv2 Qi

= Release rate of radionuclide "i" from VV-1 Auxiliary Building, uCi/sec.

vvl Q.

= Release rate of radionuclide "i" from VV-2, uCi/sec.

1 vv2 Q.

= Release rate of radionuclide "i" from TV-2, uCi/sec.

1 tv2 Q.

= Release rate of radionuclide "i" from CB-2, uCi/sec.

1 cb Q.

= Release rate of radionuclide "i" from DV-2, uCi/sec.

1 dv2 Q.

= Release rate of radionuclide "i" from WV-2, uCi/sec.

1 wv2

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(X/Q)pv (X/Q)cv (X/Q)vv (X/Q)tv (X/Q)cb (X/Q)dv (X/Q)wv

=

39 nf 131 Highest calculated annual average relative concentration for releases from the PV-1/2, sec/m3*

Highest calculated annual average relative concentration for releases from CV-I and CV-2, sec/m3*

Highest calculated annual average relative concentration for releases from VV-1 and VV-2, sec/m3*

Highest calculated annual average relative concentration for releases for TV-2, sec/m3*

Highest calculated annual average relative concentration for releases for CB-2, sec/m3*

Highest calculated annual average relative concentration for releases for DV-2, sec/m3*

Highest calculated annual average relative concentration for releases for WV-2, sec/m3*

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 of release 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 1, 2, and 3, the controlling location for implementation ofODCM 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)

EViQ,__ + :EKt [9.24E - 5 ~ Qt 1 + 1.03E - 4 Qt 1 + 9.24E - 5 Qt 7 +

t

~

t

~

w

~

7.3SE - 5 Qt 2 ]

~ S00mrem/yr cb

[2.2-5]

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40 of 111 8.2.1.4 Skin Dose Rate (at 0.35 Miles NW}

L [7.0E - 10 ~ Lt + 1.1Bt] Qtpt, L [Lt + 1.1Mt] + 9.24£ - 5 Qtcv1 + 1.03E t

t

-4 Q'vvt + 9.24£ - 5 Qtc:i,2 + 1.03E - 4 Qtw1, + 7.35E - 5 Qtcv2 + 9.24£ - 5 Qtcw2

+

[2.2-6]

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 2.2-4] become:

8.2.1.5 Total Body Dose Rate (at 0.75 Miles N)

L Vi Q,_ + L Kt [3.95E - 6 QL1 + 4.99£ - 6 Qi 1 + 3.95£ - 6 Qt_~ + 4.99£ t

-ptl i

CV-17tl CV-

< 500 ~ mrem/yr

[2.2-7]

8.2.1.6 Skin Dose Rate (at 0.75 Miles N)

L [2.31E - 6 Lt + 1.1B,] Qiy., + L [Li + 1.lMi] [3.95E - 6 Q,ci,1 + 4.99E - 6 Q,w1 +

t t

Qtwi, + 4.26E - 6 Qicb] ~ :5 3000 mrem/yr

[2.2-8]

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:

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 [22-5 through 2.2-8].

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41 nf' Bl The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GAS 1 BB ( similar to NUREG-0017. (3. t.3.4) Inputs were based on operating modes of the respective plants. The code inputs utilized are presented in l/2-ODC-3.01. 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. A TI ACHMENT 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 A TI ACHMENT E Table 2.2-3. A description of their derivation is provided in l/2-0DC-3.01.

For Release Modes 1, 2, and 3, dose calculations 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 location, 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 Mode, 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 [22-5] 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_,,(3.1.3.s) were multiplied by 1E6 to convert picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.

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4?. of 131 Values for Vi and B1 for the finite plume model can be expressed as shown in Equation [2.2-9] and [2.2-10]. 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:

Bt =.!_ L L L f pc Au Ua E1 I rd j k

l Uj

[2.2-9]

where:

I

= The results of numerical integration over the plume spatial distnbution 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 m.rad)(radians) (m3) (transformation) ~16 sectors]

(sec)(Mev)(Ci.)

n: radians

[

Ci] [

sec]

1E - 6 ti.Ci 3.1SE7 yr

= 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.

fj"k = The joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless).

Ali = 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 Hi, meters -1*

The Vi factor is computed with conversion from air dose to tissue depth dose, thus:

Vi = 1.l.!_LL L fJk Au Ua E1 le -UT Td Td j k

l Uj

[2.2-10]

where:

UT = The tissue energy absorption coefficient for photons of energy E1, cm2/gm.

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4~ of 111 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,CJ.1.3.J) the following basic equation is used to show compliance with ODCM CONTROL 3.11.2.1.b:

L PtT [(X/Q)5 Qis + (X/Q)v Qiv]

s; 1,500 mrem/yr t

[2.2-11]

where:

Pii:

= Dose parameter for any organ i-for each identified radionuclide "i",

mrem/yr per uCi/m3.

QiB

= The release rate of radionuclide "i", in gaseous effluents from elevated releases, uCi/sec.

Qiv

= The release rate of radionuclide "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/m3*

(X/Q)v = The highest calculated annual average relative concentration at the unrestricted area boundary for ground level releases, sec/m3*

NOTE:

The dispersion parameters specified in Section 8.2.2 are limited to the site boundary as defined above.

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Mof131 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/Q)tv = Highest calculated annual average relative concentration for releases from TV-2, sec/m3*

(X/Q) cb = 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 Qi

= Long-term release rate of radionuclide "i" from CV-1, uCi/sec.

cvl

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.d." nf 1 ~ 1 Qi

= Long-term release rate of radionuclide "i" from CV-2, uCi/sec.

cv2 Q.

= Long-term release rate of radionuclide "i" from VV-1, uCi/sec.

1vvl Q.

= Long-term release rate of radionuclide "i" from VV-2, uCi/sec.

1vv2 Q.

= Long-term release rate of radionuclide "i" from TV-2, uCi/sec.

1tv2 Q.

= Long-term release rate of radionuclide "i" from CB-2, uCi/sec.

1cb2 Q.

= Long-term release rate of radionuclide "i" from DV-2, uCi/sec.

1dv2 Q.

= Long-term release rate of radionuclide "i" from WV-2, uCi/sec.

lwv2 All other terms are the same as those defined previously.

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.C3*1.3.1) For the child age group, the following equation was used for all nuclides. The Pi-r, values are presented in ATTACHMENT H Table 2.2-13.

[22-13]

where:

3.7E9 =

Breathing rate of child (3,700 m3/yr) x unit conversion factor (1E6 pCi/uCi).

DFAi-r =

The organ inhalation dose factor for a child from Table 6 ofNUREG-0172 (3.l.3.6) or ERS-LMR-15-006 (3.1.32S) (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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46 nf 131 Equation [2.2-12] becomes:

8.2.2.1 L Pi-r [7.00E - 10 Qt,n, + 9.24E - 5 Q1.ci,i + 1.03E - 4 Qtwi + 7.3SE - 5 Qitvt +

t 9.24E - 5 Qfwl + 1.03E - 4 Qt..nn, + 7.35E - 5 Qft...2 + 7.3SE - 5 Qlcbz + 9.24E - 5 Q~112 + 9.24E - 5 Qiwuz]

5; 1500 mrem/yr

[2.2-14]

Determination of Controlling Location The determination of the controlling location for implementation ofODCM 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 Ptt 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.

8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)

(Gaaeous)

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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47 of 131 8.3.1 Dose Due To Noble Gases 8.3.1.1 Cumulation Of Doses 8.3.1.1.1 8.3.1.1.2 8.3.1.1.3 8.3.1.1.4 8.3.1.1.5 Section 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 of radwaste 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*13*1> the air dose limits in the umestricted area due to noble gases released in gaseous effluents are defined by the following equations:

Gamma Radiation Quarter Limit Beta Radiation Quarter Limit

[2.3-2]

Gamma Radiation Year Limit

[2.3-3]

Beta Radiation Year Limit

[2.3-4]

Gamma Radiation Projection Averaged Over 31 Days

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.d.R nf' 111 8.3.1.1.6 where:

Beta Radiation Projection Averaged Over 31 Days

[2.3-6]

= 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/Q)v = 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) 11 = 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).

qi.s

= Release of noble gas radionuclide "i" in gaseous effiuents for short-term stack releases equal to or less than 500 hrs/year (uCi).

qiv

= Release of noble gas radionuclide "i" in gaseous effiuents for short-term vent releases equal to or less than 500 hrs/year (uCi).

Qa

= Release of noble gas radionuclide "i" in gaseous effiuents 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 (mra.d/yr per uCi/sec).

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49 nf 111 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.l 7E-8 = The inverse of the number of seconds in a year.

NUREG 0133(3.l.3.l) 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 GASP AR 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 [Mt [(X/Q)cvQicv + (X/Q)wQ4n, + (X/Q)cbQicb + (X/Q)dvQidt1 +

i

~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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50 of 131 11 8.3.1.1.8 Beta Radiation Dose Equation (X/Q)tvQtw + (X/Q)wvQt\\W + 0.5 (X/Q)pvQtpv]

~ 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) vv = Annual average relative concentration for releases from VV-1 and VV-2 (sec/m3).

(X/Q)pv = 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).

Qi

= Release of radionuclide "i" from CV-1 and CV-2 (uCi).

CV Qi

= Release or radionuclide "i" from VV-1 and VV-2 (uCi).

vv Q.

= Release of radionuclide "i" from PV-1/2 (uCi).

1 pv Qi

= Release ofradionucli4e "i" from TV-2 (uCi).

tv Qi

= Release of radionuclide "i" from the CB-2 (uCi).

cb Qi

= Release of radionuclide "i" from DV-2 (uCi).

dv Qi

= Release of radionuclide "i" from WV-2 (uCi).

WV

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51 nf 13]

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 3.17E-8 L [Mt[9.24E - 5 Qici, + 1.03E - 4 Qivi, + 7.35E-5 Qitp + 7.35E - 5 Q'-cb +

i 9.24E - 5 Qt'"' + 9.24E - 5 Qi_] + 0.5 BtQty,,

S 0.2 mrad (per 31 days), or

[2.3-9]

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 Nt[9.24E - S Qicr, + 1.03E-4 Qin + 7.35E-5 Qltp + 7.35E-5 Q'-cb +

i 9.24E - 5 Qiif 11 + 9.24E - 5 Qi_ + (0.5) 7.0E - 10 Qty,,]

S 0.4 mrad (per 31 days), or

[2.3-10]

S 10.0 mrad (per quarter), or

S 20.0 mrad (per year) 8.3.1.1.11 Determination of Controlling Location The determination of the controlling locations for implementation of 10 CFR 50 is a function of the following parameters:

Radionuclide mix and their isotopic release 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 1/2-ODC-3.0l for inputs) and are shown in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.

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'-i? of 131 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 of X/Q were obtained for the midpoint of the 10 standard distance intervals previously presented in A IT ACHMENT F Tables 2.2-4 through 2.2-10.

For each Release Mode, a particular combination of Release Point mix and meteorology dominates in the 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 N1, which were used in the determination of the controlling location and which are to be used by BV-1 and BV-2 in Equations [2.3-9] and

[2.3-10] to show compliance with 10 CFR 50 were presented in A IT ACHMENT G Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, Revision 1 (3.!3.5) 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 B1 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 Dy :S 5.0 mrad Dp :S 10 mrad For The Calendar Year Dr:S 10 mrad Dp :S20 mrad where:

Dy = The air dose from gamma radiation (mrad).

Dp = The air dose from beta radiation (mrad).

[2.3-11]

[2.3-12]

[2.3-13]

[2.3-14]

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~~ of 131 8.3.1.2 8.3.1.2.1 8.3.1.2.2 The quarterly limits given above represent one-half the annual design objective of Section 11.B.1 of Appendix I of 10 CPR 50. If any of the limits of Equations

[2.3-11] through [2.3-14] are exceeded, a special report pursuant to both Section N.A of Appendix I of 10 CPR 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=s0.2mrad D~ =s 0.4 mrad Projection 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 [2.3-10] 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]

When Not Including Pre-Release Data, D31 -

[~] (31) + C

[2.3-18]

where:

DJ1

= 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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<':iA. of 131 C

= Value which may be used to anticipate plant trends (mrad).

8.3.2 Dose Due To Radioiodines And Particulates 8.32.1 8.3.2.1.1 Cumulation Of DosesSection II.C of Appendix I of 10 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,C3-13.I) 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

[2.3-19]

~ 7.5 mrem (per quarter), or

~ 15.0 mrem (per calendar year) where:

Qi.a

= Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs/yr (uCi).

Q1v

= 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).

q1v

= Release of radionuclide "i" for short-term vent releases equal to or less than 500 hrs/yr (uCi).

Ws

= 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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55 of 131 8.3.2.1.2 W v

= 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.

Wa

= 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, (DI q),.

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, (XI 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-r

= 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).

I Radionuclides and particulates may be released from any of the BV-1 and BV-2 Release Points in the Release Modes identified in A TI ACHMENT I Table 2.3-1. As descnbed previously in Section 8.3.1.1, NUREG 0133(3.!3.I) permits use oflong-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

[2.3-20]

~ 0.3 mrem (per 31 days), or

~ 7.5 mrem (pei'quarter), or

~ 15.0 mrem (per calendar year)

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°'6 nf 131 where:

0.5 Wpv Wvv Wtv Wwv Q.

1 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-1 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 of radionuclide "i" from PV-1/2 (uCi).

Qi

= Release of radionuclide "i" from CV-1 and CV-2 (uCi).

CV Qi

= Release of radionuclide "i" from VV-1 and VV-2 (uCi).

vv Q.

= Release of radionuclide "i" from TV-2 (uCi).

1 tv Qi

= Release of radionuclide "i" from CB-2 (uCi).

cb Qi

= Release of radionuclide "i" from DV-2 (uCi).

dv Qi

= Release of radionuclide "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 ofD/Q. If the inhalation pathway is considered, Wis in terms ofX/Q.

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8.3.2.1.2.1 11 57 nf 111 Incorporation of the various pathways into Equation [2.3-20] results in the following equation for a particular organ:

Radloiodines and Particulates Dose Determination 3.17E - 8 t ((Ri-ra + Ri-r,., + Ri-rv + Ri-r8 ] [0.5 WpvQi,n, + WC11Qia, +

WnQfw +.=-+ Wi-vQtn, + WcbQfcb + WdvQLcti, + WwvQtwi,]

+.=-+.=-+ Rt-r1 [0.5 (X/Q)pvQi,n, + (X/Q}CIIQfc,, + (X/Q)1111Qiw +

(X/Q)wQtn, + (X ~~/Q)cbQfcb + (X/Q)dvQtctt, + (X/Q)wv

[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 "-r" for radionuclide "i" for the ground l'to R.

l"t M plane exposure pathway (mrem/yr per uCi/sec per m-2).

=

Dose factor for an organ "-r" for radionuclide "i" for either the cow milk or goat milk pathway (mrem/yr per uCi/sec perm-2).

R.

= Dose factor for an organ "-r" for radionuclide "i" for the l'ty vegetable pathway (mrem/yr per uCi/sec per m-2).

R.

= Dose factor for an organ "-r" for radionuclide "i" for the meat l't B pathway (mrem/yr per uCi/sec per m-2).

R.

= Dose factor for an organ "-r" for radionuclide "i" for the l't I inhalation pathway (mrem/yr per uCi/m3).

It should be noted that W pv, W cv, W vv, W tv, W cp, W r1v, and W wv in Equation

[2.3-21] are in terms ofD/Q(m-2).

Values of the dose factor, R.rt, were calculated using the methodology of NUREG-0133.(3.U.l) The following equations are used for all nuclides, unless specifically listed for tritium or carbon-14:

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~R nf 111 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).

[2.3-22]

(BR)a

= The breathing rate of the receptor of age group "a" (m3/yr).

(DF Aii)a = Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem/pCi). Inhalation dose factors (DFAit) by organ for the various age groups are given in Table E-7 through E-10 of Regulatory Guide 1.109, Rev. 1 (3.I.3.5) or Tables 5 through 8 of NUREG-0172 (3.l.3.6) or ERS-LMR-15-006 (3.1.3.28) 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 1.109.(3.1.3.5)

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).

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59 nf 131 8.3.2.1.2.4 t

= The exposure time (4.73E8 sec or 15 years).

DFGi-r

= The grmmdplane dose conversion factor for organ "-r" for the "i" th radionuclide (mrem/hr per pCi/m.2). A tabulation ofDFGi-r values is presented in Table E-6 of Regulatory Guide 1.109.<3*13*5) or ERS-LMR-15-006 <3-13.28) for Se-75.

SF

= The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used.<3*1.3.S)

Dose Factors For Cow Milk or Goat Mille 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.

(DF'Lt)a = The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem/pCi).

Ingestion dose factors (DFL-r)a for the various age groups are given in Table E-11 through E-14 of Regulatory Guide 1.109(3.13.S) or Tables 1 through 4 ofNUREG-0172 (3.1.3.6) or ERS-LMR-15-006 <3.1.3.28) for Se-75.

Ai

= The decay constant for the "i" th radionuclide (sec-1).

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60 nf 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).

tb

= 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).

f's

= 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.s)

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)

Uep (liters/yr) - infant 330 E-5 child 330 E-5 teen 400 E-5 adult 310 E-5 (DLFi-r)a (mrem/pCi) each radionuclide E-11 to E-14 Yp (kg/m2) 0.7 E-15 Y, (kg/m2) 2.0 E-15 tr (seconds) 1.73E5 (2 days)

E-15 tb (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 nf 131 For goat's milk, all values remain the same except for Qp, which is 6 kg/day.

8.3.2.1.2.5 Dose Facton For Meat Pathway

= m2 -mrem/yr per uCi/sec where:

Fr

= The stable element transfer coefficients (days/kg).

Uap = The receptor's meat consumption rate for age "a" (kg/yr).

[2.3-25]

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.u.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 u ap (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 Facton For Vegetation Pathway Rt-rv = K' [Yv(A/? Aw)] (DFLt-r)a[U~fLe -lf L + U~f9e -ltth]

= m2 -mrem/yr per uCi/sec

[2.3-26]

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I".? nf 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.<3.1 3.s)

Parameter Value RG-1.109 Table r(dimensionless) 1.0 for radioiodines E-15 0.2 for particulates E-15 (DFLr)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

infant 0

E-5 U a (kg/yr) -

child 520 E-5 teen 630 E-5 adult 520 E-5 ft (dimensionless) 1.0 E-15

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h1 oft31 Parameter F g (dimensionless) tr, (seconds) th_ (seconds)

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 AB discussed in Section 8.2.2 for tritium, the parameter W for the food pathway is based upon X/Q. 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 3.17E - 8 (Rr-ru + Rr-ry + Rr-r8 + Rr-r1) [0.5 (X/Q)p11Qrpv + -(X/Q)cvQrcv +

(X/Q)wQr_ + (X/Q)ti,QTtv + (X/Q)cbQTcb + (X/Q)d11Q-rdv + (X/Q)w,,Q-rwv]

[23-Zl]

where:

RT'tM = Dose factor for organ "'t" for tritium for the milk pathway (mrem/yr per uCi/m3).

RT'tv = Dose factor for organ "'t" for tritium for the vegetable pathway (mrem/yr per uCi/m3).

RT'tB = Dose factor for organ "'t" for tritium for the beef pathway (mrem/yr per uCi/m3).

R T't1 = Dose factor for organ "'t" 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-ODC-2.04.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RTTM is basedcn[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

[2.3-28]

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.

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 RrrM.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rttv is based on [X/Q]:

8.3.2.1.2.9 Tritium Dose Factors For Vegetation Pathway Rr-rv = K'K~[U~fL + U~f9 ] (DFLt-r)a [0.75(0.5/H)]

= m.rem/yr per uCi/m3 where all terms have been defined above.

[2.3-29]

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R T't"B is based en [X,Q]:

8.3.2.1.2.10 Tritium Dose Factors For Beef Pathway Rr-r8 = K'K"FtQFUap(DFLi-r)a [0.75(0.5/H)]

= mrem/yr per uCi/m3 where all terms have been defined above.

[2.3-30]

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,;;~ of n 1 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 program, 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 Ra is basedm[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 (pRCTN + pRCTV + pRCT8 + RCT1) [0.5 (X/Q)pvQep,, + (X/Q)CtJQCep +

(X/Q)rn,Qe-,,., + (X/Q)tt,Qctt, + (X/Q)cbQccb + (X/Q)dvQcd:11 + (X/Q)wvQcwi,]

NOTE:

[2.3-31]

where:

R

= Dose factor for an organ "'t" for carbon-14 for either the cow C'tM milk or goat milk pathway mrem/yr per uCi/m3).

R

= Dose factor for an organ "'t" for carbon-14 for the vegetable Ctv pathway (mrem/yr per uCi/m3).

R

= Dose factor for an organ "'t" for carbon-14 for the meat C'tB pathway (mrem/yr per uCi/m3).

R

= Dose factor for an organ "'t" for carbon-14 for the inhalation C'tr pathway (mrem/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 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br />).

Under this condition, p should never exceed 1. For continuous releases, p = 1.

Because photosynthesis only occurs during daylight hours, it may be acceptable to take this into further consideration.

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fill of 131 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 Rc-r,., = K'K"FmQFUap(DFLt-r)a(0.11/0.16)

= 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 Rt-r8 = K'K"FtQFUap(DFLi-r)a(0.11/0.16)

= mrem/yr per uCi/m3 where all terms have been defined above.

Carbon-14 Dose Factors For Vegetation Pathway

= mrem/yr per uCi/m3 where all other terms have been defined above.

[2.3-33]

[2.3-34]

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67 nf 131 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 Qlvv + 1.SSE - 8 Qlc-,, + 1.SSE - 8 Qlcb + 1.S6E - 8 Q,dt1 + 1.56E - 8 Qtwi,] + Rt-r:1 [(0.5) 7.30E - 9 Q,pll + 2.00E - 5 Qia + 2.71E - 5 Qlvv

+ 2.22E - 5 Qlc-,, + 2.22E - 5 Qicb +,2.00E - S Qidt1 + 2.00E - 5 Qtwi,]

s_ 0.3 mrem (per 31 days), or

~ 7.5 mrem (per quarter), or

~15.0 mrem (per year)

[2.3-35]

For tritium, for purposes of implementation of 40 CFR 190, as discussed in l/2-ODC-2.04, Equation [2.3-28] reduces to:

3.17E - 8 [Rr-r:v + Rr-r:1] [(0.S)7.30E - 9 Q~ + 2.00E - 5 Qici, + 2.71E -5 8.3.2.1.4 Qlvv + 2.22E - 5 Qlc-,, + 2.22E - 5 Qicb + 2.00E - SQ~ll +

[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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fi~ nf 131 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 radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in ATTACHMENT D Tables 22-2a 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.

7 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 22-2b 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 Rt 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 descnbed in NUREG-0133(3.1.3.1) 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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69 nfBl 8.3.2.2 11 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:

Dr :S 7.5 mrem to anr organ For The Calendar Year:

D-r :S 15 mrem to any organ where:

[2.3-37]

[2.3-38]

Dr = The dose to any organ from radioiodines and particulates (mrem).

The quarterly limits given above represent one-half the annual design objective of Section Il.C of Appendix I of 10 CPR 50. If any of the limits of Equations

[2.3-33] and [2.3-34] are exceeded, a Special Report pursuant to both Section N.A of Appendix I of 10 CPR 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 ofradioiodines 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 ofHl 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,

[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).

8.4 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 efiluent Release Points is provided as A TI ACHMENT 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: Degasiften 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 Chlllen There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.

GW-1 TK-3A thru 3D: Gaseous Waste Charcoal Delay Beds There are four Charcoal Beds. The dry efiluent 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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71 of131 8.4.1.4 8.4.1.5 8.4.1.6 8.4.1.7 8.4.1.8 11 radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.

GW-1FL-5A/5B: Overhead Gu Compressor Prefflten 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/1B: Gas Compreuon There are two Compressors. The waste gas enters one of the compressors after 1 passing through the Prefilters.

GW-1 TK-2: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity *of 52 cu.ft. 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 cu.ft. 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 Moniton There are redundant Radiation Monitors on the combined PV-1/2 Gaseous W aste./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-lGW-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-108B 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 Chillen

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72 of 131 8.4.2.3 8.4.2.4 8.42.5 8.42.6 8.4.2.7 8.4.2.8 There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases fro~ the degasifiers are directed by system pressure to the Waste Gas Chillers.

2GWS-TK22A thru 22D: Waste Ga1 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 ofradioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.

2GWS-FL T24A/24B: Overhead Gas Compressor Prefflters 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: Ga1 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 cu.ft. 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 cu.ft. 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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11 73 of 131 ATTACHMENT A Page 1 of2 GASEOUS SOURCE TERM TABLE 2.1-la BV-1 RADIONUCLIDE M1X FOR GASEOUS EFFLUENTS (Ci/yt;)

RX AUXILIARY CONTAINMENT/

BUIIDING SLCRSVENT VENT GASEOUS W ASTFIPROCESS VENT Long Term, And AUXILIARY MAIN CONTAINMENT GASEOUS CONTAINMENT BUIIDINO CONDENSER/

VACUUM WASTE NUCLJD£<2)

~UIIDINQ(1)

VENTILATION AIR.EJECTOR PUMPSC3>

SYSTEM Short Term Long Term Long Term Long Term Short Term Kr-83m 2.2E-02 4.2E-01 2.7E-Ol 5.2E-03 0.0 Kr-85m 1.SE-01 l.9E+o0 1.2E+o0 5.SE-02 73E-02 Kr-85 6.lE+ol 2.5E+oo l.6E-+-OO 1.0E-+-01 2.3E+o2 Kr-87 5.4E-02 13E+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 1.2£.-01 7.7E-02 4.3E-05 0.0 X6-13lm 7.4E-01 UE-01 8.0E-02 1.8E-01 13E+oo Xe-133m 8.9E-01 8.9£.-01 5.6E--Ol 3.lE-01 0.0 Xe-133 8.9E-+-01 3.6E+ol 2.3E-+-01 2.7E-+-01 2.3E+ol Xe-135m 4.SE-03 3.2£.-01 2.0E-01 6.2E-04 0.0 Xe-135 7.0E-01 4.5E+oo 2.8E-+-OO 2.7E-01 0.0 Xe-137 1.0E-03 2.lE--01 1.3E-Ol 8.8E-05 0.0 Xe-138 l.SE-02 l.lE+oo 6.6E-01 1.7E-03 0.0 Ar-41 2.SE-+-01 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), orPV-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.l. l.5) (3.1.1.S) (3.1.3.lO)

Beaver Valley Power Station Procedure Number:

l/2-ODC-2.02

Title:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 74nf'B1 ATTACHMENT A Page 2 of2 GASEOUS SOURCE TERM TABLE 2.1-lb BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

SLCRS SLCRS TURBINE UNFILTERED FILTERED BUILDING PATHWAY fATHWAY VENT GAsgous w ASTF.IPROCESS VENT Long Term, And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER/

VACUUM WASTE NUCLIDE<2>

BUILDING<1> VENTILATION VENTILATION AIREJECTQR PUMP~C3>

SYSTEM Short Term Long Term Long Term Long Term Long Tenn Short Tenn Kr-83m 4.0E-05 4.2E-Ol 3.9E-05 2.7E-Ol 3.7E-04 0.0 Kr-85m l.4E-02 l.9E+oo l.7E-04 l.2E+oo 3.9E-03 12E-02 Kr-85 6.lE+ol 2.5E+oo 2.3E-04 l.6E+o0 72E-01 23E+-02 Kr-87 53E-06 1.3E+oo 1.lE-04 82E-01 7.8E-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 1.2E-01 1.lE-05 7.7E-02 3.lE-06 0.0 Xe-131m 72E-Ol l.3E-Ol 12E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 1.6E-0l 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-Ol 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 63E-06 0.0 Xe-138 0.0 1.lE+oo 9.7E-05 6.6E-01 12E-04 0.0 Ar-41 2.SE+-01 0.0 0.0 0.0 0.0 0.0 (I) 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 11.32(3.t.23 )

(3) Source Term from Calculation No. UR(B)-262(3.I.2.5)

Beaver Valley Power Station Titk:

ODCM: GASEOUS EFFLUENTS ATTACHMENT B Page 1 of2 Procedure Number:

l/2-0DC-2.02 Unit 1/2 Reviaioo:

11 Level Of Use:

General Skill Reference Page Number:

75 nf131 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2a BV-1 MONITOR DETECTOR EFFICIENCIES GASEOUS W ASTFl RxCONTAINMENT/

NUCLID;g AUXILIARY BUILDINQ VENT PRQCESS VENT -

SLCRSVENT PRIMARY ALTERNATE PRIMARY ALTERNATE PRIMARY ALTERNATE MONITOR<1>

MONITOR<2>

MONITOR(2)

MONITOR0>

MONITOR<1>

MONITOR<2l RM-VS-109 RM-VS-lOlB 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)

Kr-83m Kr-85m 1.14 ES 7.16 E7 9.00E7 1.14 E5 1.14 E5 4.92 E7 Kr-85 1.14 E5 8.59 E7 3.56E5 1.14 E5 1.14 E5 5.91 E7 Kr-87 1.77 E5 1.12 E8 6.78 E7 1.77 E5 1.77 ES 7.72 E7 Kr-88 1.05 E5 6.86 E7 1.05 E8 1.05 E5 1.05 E5 4.72E7 Kr-89 1.89 ES 8.81 E7 1.28 E8 1.89 E5 1.89 E5 6.06E7 Kr-90 1.89 E4 1.12 E8 1.23 E8 1.89 E4 1.89 E4 7.72 E7 Xe-131m 7.22 E4 5.89 E4 2.07 E6 7.22 E4 7.22 E4 4.05 E4 Xe-133m 1.28 E5 9.60 E5 1.16 E7 1.28 E5 1.28 ES 6.61 E5 Xe-133 4.39 E4 3.05 E7 9.24 E6 4.39 E4 4.39 E4 2.10 E7 Xc-135m 3.28 E4 1.43 E7 6.58 E7 3.28 E4 3.28 E4 9.85 E6 Xe-135 137E5 9.04E7 1.03E8 137E5 1.37E5 6.22 E7 Xe-137 1.83 ES 1.16 E8 2.91 E7 1.83 E5 1.83 E5 7.98 E7 Xe-138 1.43 E5 8.98 E7 1.06 E8 1.43 E5 1.43 E5 6.18 E7 Ar-41 1.60 E5 9.51 E7 6.59 E7 1.60 E5 1.60 E5 6.56 E7 (1) Efficiencies from Calculation Package ERS-SFL-85-031. (3.1.1.4)

(2) The listed detector efficiencies for the respective alternate monitors (Victoreen) are corrected for the reduced pressures observed and documented during operation.

Beaver Valley Power Station Procedure Number:

Titlo:

ODCM: GASEOUS EFFLUENTS ATTACIIMENT B Page 2 of2 Unit:

1/2 Revision:

11 l/2-0DC-2.02 Level Of Use:

General Skill Reference Page Number:

76 nf 131 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.l-2b BV-2 MONITOR DETECTOR EFFICIENCIES

( cpm/uCi/cc)

SLCRS SLCRS WASTE OAS UNFILTERED FILTERED STORAGE DECON NUCL1DE<1>

PATHWAY PATHWAY VAULT VENT BUILDINQ VENT 2HVS-RQ101B 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 l.80E7 1.80E7 Xe-135m 7.22E6 1.55E4 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-86-026P*12.1)

Beaver Valley Power Station Procedure Numb<<:

l/2-0DC-2.02

Title:

Unit Level Of Use:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revial.on:

Page Number:

11 77 nf 131 ATTACHMENT C Page 1 of 1 DELETED Table 2.2-1

\\

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02

Title:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revilion:

Page Number:

11 7~ nf 131 ATTACHMENT D Page 1 of2 RADIONUCLIDE MIX TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

RX CONTAINMENT/

AUXILlARY SLCRSVENT BUILDING VENT GASEOUSWASTF.JPROCESSVENT Long Tenn, And AUXILlARY MAIN CONTAINMENT CONTAINMENT BUILDING CONDENSER/

VACUUMM GASEOUS NUCLID@)

BUILDINo<1>

VENTIIATION AIREJECTOR PUMPS<3>

WASTE SYSTEM Short Term Long Term Long Term Long Term Short Term K.r-83m 2.2E-02 4.2E-01 2.7E-01 5.2E-03 0.0 K.r-85m l.SE-01 l.9E+oo l.2E+oo 5.SE-02 l.2E-02 Kr-85 6.lE+-01 2.SE+oo 1.6E+-OO 1.0E+-01 2.3E+-02 K.r-87 5.4E-02 l.3E+-OO 8.2E-01 1.lE-02 0.0 K.r-88 2.4E-01 3.8E+-OO 2.4E+-OO 7.0E-02 0.0 K.r-89 4.7E-04 l.2E-01 7.7E-02 4.3E-05 0.0 Xe-131m 7.4E-01 13E-01 8.0E-02 l.SE-01 83E-01 Xe-133m 8.9E-01 8.9E-01 5.6E-01 3.lE-01 0.0 Xe-133 8.9E+-01 3.6E+-01 2.3E+-01 2.7E+ol 8.2E+-OO Xe-135m 4.SE-03 3.2E-01 2.0E-01 6.2E-04 0.0 Xe-135 7.0E-01 4.SE+-00 2.SE+-00 2.7E-01 0.0 Xe-137 1.0E-03 2.lE-01 1.3E-01 8.SE-05 0.0 Xe-138 l.5E-02 1.lE+-00 6.6E-Ol l.7E-03 0.0 1-131 1.2E-03 4.6E-02 2.lE-02 6.6E-03 0.0 1-132 0.0 0.0 0.0 3.SE-05 0.0 1-133 2.0E-04 6.7E-02 3.0E-02 l.2E-03 0.0 1-134 0.0 0.0 0.0 6.6E-06 0.0 1-135 0.0 0.0 0.0 2.0E-04 0.0 Co-58 7.SE-04 6.0E-02 0.0 2.2E-04 0.0 Co-60 3.4E-04 2.7E-02 0.0 l.0E-04 0.0 Mn-54 2.2E-04 1.SE-02 0.0 6.9E-05 0.0 Fe-59 7.SE-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 l.SE-02 0.0 6.9E-05 0.0 Cs-137 3.SE-04 3.0E-02 0.0 l.2E-04 0.0 C-14 l.0E+-00 0.0 0.0 0.0 7.0E+-00 Ar-41 2.SE+-01 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-2UFSAR Table 11.3-1 (3.1.1.2)

(3) See Note (3) from ATTACHMENT A Table 2.1-la <3.1.1.S) (3.1.1.s) (3.t3.1o)

Beaver Valley Power Station

Title:

ODCM: GASEOUS EFFLUENTS ATTACHMENTD Page2 of2 RADIONUCLIDE MIX TABLE 2.2-2b Procedure Number.

Unit 1/2 Revision; 11 l/2-0DC-2.02 Level Of Usc:

General Skill Reference Page Number:

79 nf 131 BV-2 RADIONUCLIDE M1X FOR GASEOUS EFFLUENTS (Ci/yr)

SLCRS SLCRS UNFILTERED FILTERED TIJRBINE fATHWAY PATIIWAY llUIIDING VENT GASEOUS WASTE/PROCESS VENT Long Term, And AUXILIARY TIJRBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER/

VACUUM WASTE NUCLIDEC2>

BUILD1No<1>

VENTILATION VENTIIATION AIR.EJECTOR fUMPSC3>

SYSTEM Short Term Long Term Long Term Long Term Long Tenµ Short Term Kr-83m 4.0E-05 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m l.4E-02 l.9E+oo l.7E-04 1.2E-+-O0 3.9E-03 1.2E-02 Kr-85 6.lE-+-01 2.5E-+-OO 2.3E-04 1.6E+oo 7.2E-Ol 2.3E-+-02 Kr-87 5.3E-06 l.3E-+-O0 1.IE-04 8.2E-01 7.SE-04 0.0 Kr-88 4.lE-03 3.SE+-00 3.5E-04 2.4E+-OO 5.0E-03 0.0 Kr-89 0.0 l.2E-01 1.IE-05 7.7E-02 3.lE-06 0.0 Xe-131m 7.2E-Ol l.3E-Ol l.2E-05 8.0E-02 1.3E-02 8.3E-Ol Xe-133m 7.6E-01 8.9E-01 8.IE-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E-+-01 3.6E-+-01 3.4E-03 2.3E-+-01 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-Ol 4.5E+oo 4.2E-04 2.8E+oo 1.9E-02 0.0 Xe-137 0.0 2.IE-01 2.lE-05 1.3E-01 63E-06 0.0 Xe-138 0.0 l.IE-+-00 9.7E-05 6.6E-01 1.2E-04 0.0 1-131 2.7E-05 4.6E-03 6.5E-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 l.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.8E-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 1.8E-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 l.0E-+-00 0.0 0.0 0.0 0.0 7.0E-+-00 Ar-41 2.SE-+-01 0.0 0.0 0.0 0.0 0.0 (I) 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('3.1.13>

(3) See Section 8.1.1.1

0

l TABLE2.2-3 t:I C

~

DISTANCES OF LIMITING MAXIMUM INDIVIDUAL RECEPTORS TO RELEASE POINTS (i

FOR ANNUAL X/Q VALUES

~

(meters)

~

t.o VEGETABLE t:r1 0

(t)

DOWNWIND SITE BOUNDARY"'

GARDEN MILK.COW

MILK GOAT MEAT ANIMAL RESIDENT c::::

~

Ul SECTOR GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV t:r1 (t)

~

(1)

(2) p, N

670 579 413 2,623 2,423 4,651 4,418 4,152 3,919 2,527 2,295 1---'

~

1---'

NNE 535 792 632 2,740 2,461 6,276 6,033 2,848 2,605 2,639 2,461 t:I

~

NE 490 442 327 724 901 7,741 7,526 20,760 20,545 7,741 7,526 708 790 Ul Ul

""d ENE 490 448 394 1,674 1,658 6,824 6,671 708 1,562

~

0

~

E 545 546 551 1,979 1,922 7,065 6,998 4,265 4,200 4,265 4,200 756 1,922

~ >

(t)

~

ESE 575 607 672 1,577 1,619 2,865 2,899 1,577 1,619 1,577 1,650

~ ~ ~

00 SE 575 701 815 1,835 1,961 5,729 5,848 5,729 5,848 3,299 3,420 1,835 1,961 0~ (i s-SSE 655 762 912 1,738 1,933 5,053 5,244 9,977 10,166 1,770 1,964 1,432 1,628 !~I

~-

0 r:::s s

850 887 1,054 3,138 3,372 3,347 3,539 2,253 2,487 2,189 2,423 SSW 975 1,064 1,226 2,317 2,560 3,347 3,590 5,616 5,859 2,317 2,560 1,223 1,466 t:r1 t:r1 SW 1,435 1,439 1,574 2,221 2,439 2,993 3,210 2,414 2,632 2,221 2,439

~

WSW 595 561 660 2,301 2,463 5,182 5,341 2,446 2,608 2,301 2,463 0 a w

685 640 681 3,556 3,635 5,118 5,195 4,088 4,166 3,556 3,635 WNW 810 701 676 3,605 3,590 4,538 4,521 22,529 22,507 3,605 3,590 3,605 3,590

- i..... i i NW 655 567 482 1,464 1,415 10,944 10,832 4,570 4,461 1,432 1,383 NNW 645 558 420 1,464 1,285 15,450 15,262 3,959 3,774 1,143 1,253

-~ ~

z 5!

Distances for ground releases are measured from the center point between the BV-1 and BV-2 Containment Buildings. Distances for i i[ 6 !l elevated release are measured from the BV-1 Cooling Tower. Elevated release is applicable to PV-1/2. Ground release is applicable to

~,

[Q t:I all other release points.

(i cni ~

(1) TV-2 and CB--2

[** 0

- f N

(2) W-1, CV-1, W-2, CV-2, DV-2, WV-2 w

8

TABLE2.2-4 0 i g

CV-1 AND CV-2 ANNUAL A VER.AGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES

~

(IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS

~

(lE-7 sec/m 3

)

to tI1 INDIVIDUAL RECEPTORS DISTANCES TO TIIE CONTROL LOCATION, IN MILES 0

G c::

~

tI1 G

i 1-1 DOWN-SITE VEGE-WIND BOUND TABLE MILK MILK MEAT RESI-0-

0.5-1.0-1.5-2.0-2.5-3.Q-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

G 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 2280 V,

~

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 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

~

t, G

!~~

1-1 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 CZ)

ESE 31.1 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

~in g_

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 ~-;

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 z g, 0

~~

~

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 223 13.90 -

9.050 1230 13.90 160.0 29.2 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 WSW 163.0 1930 5.720 -

17.70 1930 283.0 49.8 23.50 14.60 1030 7.72 5.690 4.650 3.620 3.090

~

~i C:

J w

278.0 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

e.

rt WNW 487.0 40.70 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

.... ~ ~

NW 924.0 194.00 8.660 40.50 200.00 1710.0 262.0 123.00 79.80 55.00 4230 34.000 28.200 19.400 16.700 NNW 302.0 63.00 -

1.720 15.40 9230 547.0 86.4 40,.80 26.20 17.60 13.50 10.100 8.350 6.560 5.660 5(

i ~[ 6*

2.Q t,

~,

n 00 !r t!.l

~- ~-- s

- i

~

TABLE2.2-5 0

g t::1

~

W-1 AND W-2 ANNUAL AVERAGE, GROUND LEVEL,

~

X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATI ACHMENT E, TABLE 2.2-3), AND SELECfED CONTROL LOCATIONS

~

(lE-7 sec/m)

U) to tr.l INDIVIDUAL RECEPTORS DISTANCES TO TIIE CONTROL LOCATION, IN MILES 0

G cj

~

U) tr.l G

I

"'"l DOWN-SITE VEGE-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.S 3.0 3.5 4.0 4.5 5.0 p, -

0 I

G N

152.0 15.00 -

S.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

~

NNE 62.3 7.66 -

2.150 7.08 1.95 189.0 32.0 12.20 7.31 4.99 3.69 2.87 2.320 1.920 1.630

~

'""d NE 132.0 57.90 1.240 0.269 1.24 60.20 156.0 24.8 12.70 7.51 5.09 3.73 2.47 1.980 1.500 1.270 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

~

9 G

~~~

"'"l 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

!~ ~

r.n ESE 38.0 7.64 3200 7.64 7.64 76.7 11.9 5.59 3.29 2.05 1.49 1.05 0.842 0.630 0.531 g_

SE 33.3 7.27 1.030 1.030 2.88 1.21 86.2 13.5 6.37 3.75 2.53 1.84 1.20 0.960 0.790 0.666 ~NI SSE 29.1 7.41 1.080 0.382 7.19 10.10 87.0 13.7 S.98 3.53 2.02 1.48 1.04 0.833 0.688 0.531 00 0

z 1-+i l::S 1~~

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 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 1260 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 22.40 347.0 613 27.70 16.60 11.40 8.49 6.19 S.020 3.880 3.300

~

=f

[ f w

345.0 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

,... rt 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 28.70 23.400 15.900 13.600 i:3 NW 1030.0 262.00 9.520 47.80 271.00 1820.0 350.0 164.00 100.00 66.60 SO.IO 39.50 32.300 21.900 18.800 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

-1 i i[

i:3 6*

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...... i

~

0 g

TABLE2.2-6

~

!l PV-1/2 ANNUAL AVERAGE, ELEVATED LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS

~

(lE-7 sec/m 3

)

t:o tI'.l 0

('I)

INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES C:

~

t:Zl tI'.l

('I)

~

1-1 DOWN-SITE VEGE-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-p)

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

('I)

VI 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

~

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 1--d 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 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 sa

~

('I)

~~~

1-1 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 r.n 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 ~ti g_

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....,

=

1~~

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 l.o30 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 !

WSW 0.126 4.350 1.420 -

3.98 4350 0.3870 17.8000 4.9000 3.53 2.36 1.64 1.460 1.210 0.920 0.781

_(.... i I 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

-~ ~

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 1.110 0.686 0.791 0.731 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 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 ~[

~

6*

[Q t:I

Elevated release X/Q value at site boundary location where ground level release X/Qs maximize.

~,

(")

f-l f N S-i. ~-- s

~

w - f CD

0

i TABLE2.2-7 t1

e.

~

TV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES

~

FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACIWENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS

~

(IE-7 sec/m 3

)

t;d tI'.1 0

(1)

INDIVIDUAL RECEPTORS DISTANCES TO TIIB CONTROL LOCATION, IN MILES C:

~

CZl I

(1) 1-1 DOWN-SITE VEGE-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-p)

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 Vi

~

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

~

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 l-0 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 0

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 t1

~

(1) ij ~ ~

1-1 Cl)

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

!~ >

Pl 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 -~;

SE 41.8 7.06 1.020 1.020 2.85 7.06 73.5 12.6 6.12 3.64 2.47 1.81 1.18 0.945 0.779 0.658

~~

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 t::s 1~~

s 32.7 3.64 3310 -

6.00 6.27 109.0 18.6 7.13 4.29 2.94 2.17 1.53 1.230 1.020 0.866 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 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

~

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

=f c:::: I

~--

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 N

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 NW 735.0 216.00 9.100 43.90 222.00 1720.0 279.0 14-0.00 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 i[

N 6*

~, la g

a, ~

tZl g ~

g** s

- I

~

Beaver Valley Power Station

Title:

ProccdoR, Number.

l/2-0DC-2.02 Unlt Level OfUae:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revilion:

Page Number:

11 R~ nf Bl ATTACHMENT F Page 5 of7 0-5 MILE DISPERSION PARAMETERS TABLE2.2-8 DV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALVES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (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

Title:

Proccdurc Number:

l/2-0DC-2.02 Unit:

Level OfU&C:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number.

11 RI\\ nf 131 ATTACHMENT F Page 6 of7 0-5 MILE DISPERSION PARAMETERS TABLE22-9 WV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALVES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (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 Titlc:

Procedure Number:

l/2-0DC-2.02 Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Rcvilion:

Page Number:

11 87 nfB1 ATTACHMENT F Page 7 of7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-10 CB-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN A IT ACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL WCA TIONS Same as Table 2.2-7

Beaver Valley Power Station Procedure Nmnber:

l/2-0DC-2.02 Titlo:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 RR nfBl 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 M1 N1 TOTAL BODY SKIN DOSE GAMMAAIR BETA AIR DOSE NUCLIDE(1)

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

" 1.93E+ol 2.88E+o2 Kr-85m 1.17E+o3 1.46E+o3 1.23E+o3 l.97E+o3 Kr-85 l.61E+ol 1.34E+o3 1.72E+ol l.95E+o3 Kr-87 5.92E+o3 9.73E+o3 6.17E+o3 l.03E+o4 Kr-88 1.47E+o4 2.37E+o3 1.52E+o4 2.93E+o3 Kr-89 1.66E+o4 1.01E+o4 1.73E+o4 1.06E+-04 Kr-90 l.56E+o4 7.29E+o3 l.63E+o4 7.83E+o3 Xe-131m 9.15E+ol 4.76E+o2 l.56E+o2 1.11E+o3 Xe-133m 2.51E+o2 9.94E+o2 3.27E+o2 1.48E+o3 Xe-133 2.94E+o2 3.06E+o2 3.53E+o2 1.05E+o3 Xe-135m 3.12E+o3 7.11E+o2 3.36E+o3 7.39E+o2 Xe-135 1.81E+o3 l.86E+o3 l.92E+o3 2.46E+o3 Xe-137 1.42E+o3 l.22E+o4 1.51E+o3 1.27E+-04 Xe-138 8.83E+o3 4.13E+o3 9.21E+o3 4.75E+o3 Ar-41 8.84E+o3 2.69E+o3 9.30E+o3 3.28E+03 (1) The listed dose factors are for radionuclides that may be detected in gaseous effluents.

Beaver Valley Power Station

Title:

Procedure Number:

l/2-0DC-2.02 Unit Level Of Use:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

NUCLIDEC4)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 11 RQ ofl'H ATTACHMENT G Page 2 of2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES yp)

TOTAL BODY DOSE FACTOR mrem/yr Per uCi/sec 3.19E-10 7.81E-5 1.55E-6 5.13E-4 1.39E-3 7.99E-4 l.64E-5 l.38E-5 1.0SE-5 2.41E-4 1.41E-4 6.00E-5 8.llE-4 1.02E-3 Bi_(l), ( 2)

GAMMA AIR DOSE FACTOR mrad/yr Per uCi/sec 1.75E-8 1.16E-4 2.35E-6 7.74E-4 2.09E-3 1.20E-3 2.47E-5 2.llE-5 1.56E-4 3.66E-4 2.12E-4 9.0SE-5 1.22E-3 1.53E-3 yp)

TOTAL BODY DOSE FACTOR mrem/yr Per uCi/sec 4.58E-8 4.70E-4 5.54E-6 1.45E-3 4.09E-3 l.25E-3 l.67E-4 l.32E-4 l.54E-4 6.21E-4 6.96E-4 9.66E-5 222E-3 2.68E-3 BP)

GAMMAAIR DOSE FACTOR mrad/yr Per uCi/sec 3.96E-5 7.06E-4 8.40E-6 2.19E-3 6.16E-3 l.88E-3 3.09E-4 2.61E-4 2.76E-4 9.50E-4 l.0SE-3 l.46E-4 3.34E-3 4.02E-3 (I) V1 and Bi values used to implement Modes 1, 2, and 3 of Section 2.2.1 (1 OCFR20)

(2) Bi values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50)

(3) V1 and Bi values to implement Mode 4 of Section 2.2.1 (1 0CFR20) and to implement monitor setpoint determinations of Section 2.1.2 and 2.1.4 C4) The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02 Title*

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Rcvwon:

Page Number:

11 Q() nf 111 ATTACHMENT H Page 1 of 1 ORGAN DOSE P ARAMETER.S Table 2.2-13 PiT VALUES FOR A CHILD FOR THE BEAVER VALLEY SITE (mrem/yr per uCi/cu meter)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.00E+00 l.12E+03 l.12E+03 l.12E+03 l.12E+03 l.12E+03 l.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 l.14E+05 9.88E+04 0.0OE+00 0.00E+00 0.00E+O0 4.22E+04 4

Cr-51 0.00E+00 0.0OE+00 l.54E+02 8.55E+0l 2.43E+0l

1. 70E+04 l.08E+03 5

Mn-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 l.00E+04 l.58E+06 2.29E+04 6 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 l.27E+06 7.07E+04 7

Co-57 0.00E+00 9.03E+02 l.07E+03 0.00E+00 0.00E+00 5.07E+05 l.32E+04 8

Co-58 0.00E+00

1. 77E+03 3.16E+03 0.00E+00 0.00E+00

1. 11E+06 3.44E+04 9

Co-60 0.00E+00

1. 31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 10 Zn-65 4.26E+04 l.13E+05 7.03E+04 0.0OE+00 7.14E+04 9.95E+05 l.63E+04 11 Se-75 0.00E+00 4.40E+03 2.17E+03 0.0OE+00 5.11E+03 6.33E+05 l.69E+04 12 Rb-86 0.00E+00 1.98E+05 l.14E+05 0.00E+00 O.00E+00 0.00E+00 7.99E+03 13 Sr-89 5.99E+05 0.OOE+00

1. 72E+04 0.0OE+00 O.00E+00 2.16E+06 l.67E+05 14 Sr-90 l.01E+08 0.00E+00 6.44E+06 0.0OE+00 O.O0E+00

1. 48E+07 3.43E+05 15 Y-91 9.14E+0S 0.0OE+00 2.44E+04 0.0OE+00 0.O0E+00 2.63E+06

1. 84E+05 16 Zr-95 l.90E+05 4.18E+o4 3.70E+04 0.0OE+00 S.96E+04 2.23E+06 6.11E+04 17 Nb-95 2.35E+04 9.18E+o3 6.55E+03 0.0OE+00 8.62E+03 6.14E+0S 3.70E+04 18 Nb-97 4.29E-01 7.70E-02 3.60E-02 0.0OE+00 8.SSE-02 3.42E+03 2.78E+04 19 Mo-99 0.00E+00

1. 72E+02 4.26E+0l O.00E+00 3.92E+02 l.35E+0S l.27E+05 20 Tc-99m

1. 78E-03 3.48E-03 5.77E-02 0.00E+00 5.07E-02 9.51E+02 4.81E+03 21 Ru-103 2.79E+03 0.0OE+00

1. 07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 22 Ru-106

1. 36E+05 0.00E+00

1. 69E+04 0.00E+00 l.84E+05 l.43E+07 4.29E+0S 23 Ag-ll0m l.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 S.48E+06

1. 00E+05 24 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.O0E+00 3.24E+06 1.64E+05 25 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.lOE+0l O.O0E+00 2.32E+06 4.03E+04 26 Sb-126 6.36E+03 9.69E+Ol 2.28E+03 3.70E+0l 0.O0E+00 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. 4BE+06 7.14E+04 28 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 S.03E+04 1.76E+06 1.82E+05 29 I-131 4.81E+04 4.B1E+04 2.73E+04 1.62E+07 7.BBE+04 O.00E+00 2.84E+03 30 I-133 1.66E+04 2.03E+04 7.70E+03 3.8SE+06 3.38E+04 O.00E+00 5.48E+03 31 Cs-134 6.SlE+0S

1. 01E+06 2.25E+05 0.00E+00 3.30E+05

1. 21E+0S 3.85E+03 32 Cs-136 6.51E+o4 1.71E+0S 1.16E+05 0.00E+00 9.SSE+04

1. 45E+04 4.18E+03 33 Ca-137 9.07E+0S 8.2SE+0S l.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 34 Ba-140 7.40E+04 6.48E+0l 4.33E+03 0.00E+0O

2. llE+0l 1.74E+06 1.02E+05 35 La-140 6.44E+02 2.25E+02 7.55E+0l 0.00E+00 0.00E+00 l.83E+05 2.26E+05 36 Ce-141 3.92E+04 1.95E+04 2.90E+03 0.00E+0O 8.55E+03 S.44E+05 S.66E+04 37,Ce-144 6.77E+06 2.12E+06 3.61E+05 0.O0E+00 1.17E+06

1. 20E+07 3.89E+05 Calculated per ODCM equation 2.2-13

Beaver Valley Power Station ODCM: GASEOUS EFFLUENTS ATTACHMENT I Page I of I Proceduro Number:

l/2-0DC-2.02 Unit 1/2 Revision:

11 Level OfUae:

General Skill Reference Page Number:

91 of 131 MODES OF GASEOUS RELEASE TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEA VER VALLEY SITE VENTS FOR IMPLEMENTATION OF IO CFR 20 AND 10 CFR 50 RELEASE RELEASE RELEASE RELEASE RELEASE POINT MODE I MODE2 MODE3 MODE4 RP 1; VV-1, Auxiliary Aux. Bldg.

Containment Same As Mode 1 Same As Mode 1 Building V ent<l)

Ventilation Purge(3)

RP 2; CV-I, Rx Leakage Collection Same As Mode 1 Same As Mode 1 Same AB Mode 1 Containment/SLCRS Vent<1> Exhaust and Containment Purge(3)

RP 3; PV-1/2, Gaseous Main Coml. Air Same As Mode 1 Same As Mode 1 Same AB Mode 1 Waste/Process V ent<2>

Ejector, Waste Gas, and Containment Containment Purge Vacuum RP'4; VV-2 SLCRS Contiguous Areas Containment Same As Mode 1 Same As Mode 1 Unfiltered Pathwa/1>

Purge(3}

RP 5; CV-2, SLCRS Filtered Aux. Bldg.

Same As Mode 1 Same As Mode 1 Same As Mode 1 Pathwa/1>

Ventilation and Containment Purge(3)

RP 6; CB-2, Condensate (4)

(4)

(-4)

(4)

Polishing Bldg vent<1>

RP 7; WV-2, Waste Gas (4)

(4)

(-4)

(4)

Storage Vault Vent<1>

RP 8; DV-2,

(-4)

(4)

(-4)

(4)

Decontamination Bldg Vent<1>

RP 9; TV-2, Turbine Bldg (4)

(4)

(-4)

(4) vent<*>

NOTE: For the purpose of implementing IO CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.

<1> Continuous ground level meteorology is applicable (2) Continuous elevated meteorology is applicable (3) Mode established by purge from one unit, all other release points remain same as Mode I

<4> Not normally a radioactive release point

Beaver Valley Power Station ProceduR, Number:

l/2-0DC-2.02

Title:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 Q? nf 131 ATTACHMENT J Page 1 of 19 P&I ORGAN DOSE FACTORS Table 2.3-2 R VALUES FOR BEAVER VALLEY SITE (mrem/yr per uCi/cu meter)

Pathway= Inhalation Age Group 0

Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.00E+00 l.26E+03 1.26E+03 1.26E+03

1. 26E+03 l.26E+03 l.26E+03 2

C-14 l.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3

P-32 l.32E+06

7. 71E+04 5.01E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+04 4 Cr-51 0.00E+00 0.00E+00 l.00E+02 5.95E+0l 2.28E+0l l.44E+04 3.32E+03 5

Mn-54 0.O0E+0O 3.96E+04 6.30E+03 0.00E+00 9.84E+03

1. 40E+06 7.74E+04 6 Fe-59 l.18E+04 2.78E+04 l.06E+04 0.00E+00 0.00E+00 l.02E+06 l.88E+05 7

Co-57 0.00E+OO 6.92E+02

6. 71E+02 0.00E+00 0.00E+00 3.70E+05 3.14E+04 8

Co-58 0.00E+00 1.58E+03 2.07E+03 0.00E+O0 0.00E+00 9.28E+05 l.06E+05 9

Co-60 O.00E+00 1.15E+04

1. 48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 10 Zn-65 3.24E+04 l.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 11 Se-75 0.00E+0O 2.97E+03 l.10E+03 0.00E+00 3.69E+03 4.11E+05 3.54E+04 12 Rb-86 0.00E+00

1. 35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 l.66E+04 13 Sr-89 3.04E+05 0.00E+00

8. 72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 14 Sr-90 9.92E+07 0.00E+O0 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 15 Y-91 4.62E+05 0.0OE+00

1. 24E+04 0.00E+00 0.00E+00

1. 70E+06 3.85E+05 16 Zr-95 l.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 l.77E+06 l.50E+05 17 Nb-95 l.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 l.04E+05 18 Nb-97 2.22E-0l 5.62E-02 2.05E-02 0.00E+00 6.54E-02 2.40E+03 2.42E+02 19 Mo-99 0.00E+00

1. 21E+02 2.30E+0l 0.00E+00 2.91E+02 9.12E+04 2.48E+05 20 Tc-99m l.03E-03 2.91E-03 3.70E-02 0.00E+00 4.42E-02 7.64E+02 4.16E+03 21 Ru-103 l.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 l.10E+05 22 Ru-106 6.91E+04 0.00E+00

8. 72E+03 0.00E+00 l.34E+05 9.36E+06 9.12E+05 23 Ag-ll0m l.08E+04 1.00E+04 5.94E+03 0.00E+00 l.97E+04 4.63E+06 3.02E+05 24 Sb-124 3.12E+04 5.89E+02 l.24E+04 7.55E+0l 0.00E+00 2.48E+06 4.06E+05 25 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+0l 0.00E+00 1.74E+06

1. 01E+05 26 Sb-126 3.60E+03 7.30E+Ol l.30E+03 2.20E+0l 0.00E+00 7.66E+05 4.81E+05 27 Te-127m 1.26E+04 5.77E+03 l.57E+03 3.29E+03 4.58E+04 9.60E+05 l.50E+05 28 Te-129m 9.76E+03 4.67E+03 l.58E+03 3.44E+03 3.66E+04 l.16E+06 3.83E+05 29 I-131 2.52E+04 3.58E+04 2.05E+04 l.19E+07 6.13E+04 0.00E+00 6.28E+03 30 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 31 Cs-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04

1. 04E+04 32 Cs-136 3.90E+04 1.46E+05

1. 10E+05 0.00E+00 8.56E+04 l.20E+04

1. l 7E+04 33 Cs-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 34 Ba-140 3.90E+04 4.90E+Ol 2.57E+03 0.0OE+00 l.67E+0l 1.27E+06 2.18E+05 35 La-140 3.44E+02 l.74E+02 4.58E+0l 0.00E+00 0.0OE+00 1.36E+05 4.58E+05 36 Ce-141

1. 99E+04 l.35E+04 l.53E+03 0.0OE+00 6.26E+03 3.62E+05 l.20E+05 37 Ce-144 3.43E+06 l.43E+06 l.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Procedure Number.

l/2-0DC-2.02 Titlc:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 93 of 111 ATTACHMENT J Page 2 of 19 P&I ORGAN DOSE FACTORS Table 2.3-3 R VALUES FOR BEAVER VALLEY SITE (mrem/yr per uCi/cu meter)

Pathway= Inhalation Age Group -

Teen Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.O0E+O0 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 0.0OE+O0 0.00E+O0 0.00E+00 9.28E+04 4 Cr-51 0.00E+00 0.00E+00 1.35E+02 7.SOE+0l 3.07E+Ol 2.10E+04 3.00E+03 5

Mn-54 0.O0E+00 5.11E+04 B.40E+03 O.00E+00 1.27E+04 1.9BE+06 6.68E+04 6 Fe-59 l.59E+04 3.70E+04

1. 43E+04 0.0OE+00 O.00E+00 1.53E+06 1.78E+05 7

Co-57 0.00E+00

9. 44E+02 9.20E+02 0.0OE+00 0.00E+00 5.86E+05 3.14E+04 8 Co-58 0.00E+00 2.07E+03 2.78E+03 0.0OE+00 0.00E+00 l.34E+06 9.52E+04 9 Co-60 0.00E+00 1.51E+04 1.98E+04 0.0OE+00 0.00E+00

8. 72E+06 2.59E+05 10 Zn-65 3.86E+04 1.34E+05 6.24E+04 0.OOE+0O B.64E+04

1. 24E+06 4.66E+04 11 Se-75 0.00E+D0 4.20E+03

1. 57E+03 O.0DE+00 5.27E+03 7.l0E+0S 3.55E+04 12 Rb-86 0.00E+00 l.90E+05 8.40E+04 O.0DE+00 0.00E+00 0.0DE+00

1. 77E+04 13 Sr-89 4.34E+05 0.0OE+00

1. 25E+04 O.00E+00 0.00E+00 2.42E+06

3. 71E+05 14 Sr-90 1.0SE+0B 0.0OE+00 6.68E+06 O.O0E+00 0.00E+00 1.65E+07 7.65E+05 15 Y-91 6.61E+05 0.0OE+00

1. 77E+04 O.00E+0O 0.00E+00 2.94E+06 4.09E+05 16 Zr-95

1. 46E+05 4.58E+04 3.15E+04 O.O0E+0O 6.74E+04 2.69E+06 l.49E+05 17 Nb-95 l.86E+04 1.03E+04 5.66E+03 O.OOE+0O 1.00E+04 7.51E+05 9.68E+04 18 Nb-97 3.14E-01 7.78E-02 2.84E-02 0.00E+O0 9.12E-02 3.93E+03 2.17E+03 19 Mo-99 0.00E+00 1.69E+02 3.22E+0l 0.0OE+O0 4.11E+02 1.54E+05 2.69E+05 20 Tc-99m 1.38E-03 3.86E-03 4.99E-02 0.0OE+0O 5.76E-02 1.15E+03 6.13E+03 21 Ru-103 2.10E+03 0.0OE+00 B.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 22 Ru-106 9.84E+04 0.0OE+00 1.24E+04 O.00E+00

1. 90E+05 1.61E+07 9.60E+05 23 Ag-ll0m 1.38E+04 l.31E+04 7.99E+03 O.00E+00 2.50E+04 6.75E+06 2.73E+05 24 Sb-124 4.30E+04 7.94E+02 1.68E+04 9.76E+0l 0.00E+0O 3.34E+06 3.9BE+05 25 Sb-125 7.38E+04 8.08E+02

1. 72E+04 7.04E+0l 0.00E+00 2.74E+06 9.92E+04 26 Sb-126 4.95E+03 1.02E+02 1.78E+03 2.80E+0l 0.D0E+0O

1. 24E+06 4.BlE+0S 27 Te-127m 1.80E+04 8.16E+03 2.1BE+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 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 30 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00

1. 03E+04 31 Ca-134 5.02E+05 l.13E+06 5.49E+05 O.O0E+O0 3.75E+05

1. 4 6E+05 9.76E+03 32 Ca-136 5.15E+04 l.94E+05

1. 37E+05 O.O0E+00 1.10E+05 l.78E+04

1. 09E+04 33 Ca-137 6.70E+05 8.48E+05 3.11E+05 O.00E+00 3.04E+05

1. 21E+05 8.48E+03 34 Ba-140 5.47E+04 6.70E+0l 3.52E+03 0.00E+00 2.28E+0l 2.03E+06 2.29E+05 35 La-140 4.79E+02 2.36E+02 6.26E+0l 0.00E+00 0.00E+00 2.14E+05 4.87E+05 36 Ce-141 2.84E+04 l.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 37 Ce-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 l.21E+06 1.34E+07 8.64E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Proccdme Number:

l/2-0DC-2.02 Trtle:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 Q.:1 of 131 ATTACHMENT J Page 3 of 19 P&I ORGAN DOSE FACTORS Table 2.3-4 R VALUES FOR BEAVER VALLEY SITE (mrem/yr per uCi/cu meter)

Pathway -

Inhalation Age Group -

Child Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 1.12E+03 1.12E+03 l.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 O.OOE+OO O.OOE+OO 4.22E+04 4 Cr-51 O.OOE+OO O.OOE+OO

1. 54E+02 8.SSE+Ol 2.43E+Ol 1.70E+04

1. 08E+03 5

Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.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 O.OOE+OO 1.27E+06 7.07E+04 7

Co-57 O.OOE+OO 9.03E+02 l.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 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 9

Co-60 O.OOE+OO

1. 31E+04 2.26E+04 O.OOE+OO O.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 O.OOE+OO 4.40E+03 2.17E+o3 O.OOE+OO 5.llE+D3 6.33E+05 1.69E+04 12 Rb-86 O.OOE+OO l.98E+OS 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 13 Sr-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 14 Sr-90 1.0lE+D8 O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO

1. 4 8E+07 3.43E+OS 15 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06

1. 84E+05 16 Zr-95 1.90E+05 4.18E+o4 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-Ol 7.70E-02 3.60E-02 O.OOE+OO 8.55E-02 3.42E+03 2.78E+04 19 Mo-99 O.OOE+OO

1. 72E+02 4.26E+Ol 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-02 9.SlE+D2 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-llOm 1.69E+04

1. 14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+D5 24 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 25 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.lOE+Ol O.OOE+OO 2.32E+06 4.03E+04 26 Sb-126 6.36E+03 9.69E+Ol 2.28E+03 3.70E+Ol O.OOE+OO l.06E+06 2.lOE+D5 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+o4 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 30 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.4BE+03 31 Cs-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+OO 3.30E+05 l.21E+05 3.B5E+03 32 Cs-136 6.51E+04

1. 71E+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+OS O.OOE+OO 2.82E+OS 1.04E+05 3.62E+03 34 Ba-140 7.40E+04 6.48E+Ol 4.33E+03 O.OOE+OO

2. llE+Ol

1. 74E+06 1.02E+05 35 La-140 6.44E+02 2.25E+02 7.55E+Ol 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+OS O.OOE+OO 1.17E+06 1.20E+07 3.89E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Procedure N~

l/2-0DC-2.02

Title:

Unit LcvolOfUae:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS R.cvia.ion:

11 Page Number:

95ofl31 ATTACHMENT J Page4 of 19 P&I ORGAN DOSE FACTORS Table 2.3-5 R VALUES FOR BEAVER VALLEY SITE (mrem/yr per uCi/cu meter)

Pathway= Inhalation Age Group -

Infant Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-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 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 3

P-32 2.03E+06 l.12E+05 7.74E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 4 Cr-51 O.OOE+OO O.OOE+OO 8.95E+Ol 5.75E+Ol 1.32E+Ol

1. 28E+04 3.57E+02 5

Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+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 O.OOE+OO 3.79E+05 4.86E+03 8 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11E+04 9 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.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 O.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+OS 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 13 Sr-89 3.98E+05 O.OOE+OO 1.14E+04 0.00E+OO O.OOE+OO 2.03E+06 6.40E+04 14 Sr-90 4.09E+07 O.OOE+OO 2.59E+06 O.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 O.OOE+OO 2.45E+06 7.03E+04 16 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11E+04 1.75E+06 2.17E+04 17 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05

1. 27E+04 18 Nb-97 3.42E-01 7.29E-02 2.63E-02 O.OOE+OO 5.70E-02 3.32E+03 2.69E+04 19 Mo-99 O.OOE+OO l.65E+02 3.23E+Ol O.OOE+OO 2.65E+02 1.35E+05 4.87E+04 20 Tc-99m

1. 40E-03 2.88E-03 3.72E-02 O.OOE+OO

3. llE-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 l.16E+07 1.64E+05 23 Ag-llOm 9.98E+03 7.22E+03 5.00E+03 O.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+Ol O.OOE+OO 1.64E+06 1.47E+04 26 Sb-126 4.31E+03 8.41E+Ol 1.55E+03 3.29E+Ol 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 4.21E+03 3.18E+04 1.68E+06 6.90E+04 29 I-131 3.79E+04 4.44E+04

1. 96E+04 1.48E+07 5.18E+o4 O.OOE+OO

1. 06E+03 30 I-133 1.32E+04 l.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 l.18E+04 1.43E+03 33 Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO

1. 72E+05 7.13E+04 1.33E+03 34 Ba-140 5.60E+04 5.60E+Ol 2.90E+03 O.OOE+OO

1. 34E+Ol

1. 60E+06 3.84E+04 35 La-140 5.05E+02 2.00E+02 5.15E+Ol O.OOE+OO O.OOE+OO l.68E+05 8.48E+04 36 Ce-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 37 Ce-144 3.19E+06 1.21E+06

1. 76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Procedure Number.

l/2-ODC-2.02

Title:

Unit Level OfUso:

l/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 96 ofH1 ATTACHMENT J Page 5 of 19 P&I ORGAN DOSE FACTORS Table 2.3-6 R VALUES FOR BEA VER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway -

Ground Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.00E+0O 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2

C-14 0.O0E+00 0.00E+00 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3

P-32 0.O0E+0O 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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

Mn-54

1. 39E+09 l.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.00E+0O 0.00E+00 0.00E+0O 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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

Co-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.lSE+l0 2.15E+10

2. lSE+l0 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 0.00E+00 0.00E+O0 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 Nb-95 l.37E+08

1. 37E+08

1. 37E+08 l.37E+08 1.37E+08 1.37E+08 1.37E+08 18 Nb-97 0.O0E+OO 0.0OE+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 19 Mo-99 4.00E+06 4.00E+06 4.00E+06 4.00E+06 4.00E+06 4.00E+06 4.00E+06 20 Tc-99m 1.84E+05 1.84E+05 1.84E+0S 1.84E+05 1.84E+0S 1.84E+05

1. 84E+0S 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-ll0m 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 24 Sb-124 0.00E+00 0.00E+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 25 Sb-125 0.00E+00 0.00E+00 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 26 Sb-126 0.O0E+00 0.00E+O0 0.OOE+00 0.00E+00 0.00E+00 0.00E+O0 0.00E+00 27 Te-127m 9.17E+04 9.17E+04 9.17E+o4 9.17E+04 9.17E+04 9.17E+04 9.17E+04 28 Te-129m l.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 l.72E+07 30 I-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 l.51E+08 1.51E+08 1.51E+08 l.51E+08 l.51E+08 1.51E+08 1.51E+08 33 Cs-137 1.03E+10

1. 03E+10

1. 03E+l0 1.03E+l0 l.03E+l0 1.03E+l0

1. 03E+10 34 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.0SE+07 2.0SE+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 l.92E+07 36 Ce-141 1.37E+07

1. 37E+07 l.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 Calculated per ODCM equation 2.3-23

Beaver Valley Power Station Procodure Number.

l/2-ODC-2.02 Titlc:

Unit Level OfU1e:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 97 of nt ATTACHMENT J Page 6 of 19 r

P&I ORGAN DOSE FACTORS Table 2.3-7 R VALUES FOR BEAVER VALLEY SITE (aq meter-mrem/yr per uCi/aec)

Pathway* Vegetation Age Group

Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2

C-14 8.97E+05 1.79E+05 1.79E+05 1.79E+05

1. 79E+05 1.79E+05 1.79E+05 3

P-32

1. 40E+09 8.74E+07 5.43E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+08 4 Cr-51 O.OOE+OO O.OOE+OO 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 5

Mn-54 O.OOE+OO 3.13E+08 5.97E+07 O.OOE+OO 9.31E+07 O.OOE+OO 9.59E+08 6 Fe-59 l.26E+08 2.96E+08 1.14E+08 O.OOE+OO O.OOE+OO 8.28E+07 9.88E+08 7

Co-57 O.OOE+OO 1.17E+07 1.95E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+08 8

Co-:-58 O.OOE+OO 3.07E+07 6.89E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 9 Co-60 O.OOE+OO

1. 67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 10 Zn-65 3.17E+08 1.01E+09 4.56E+08 O.OOE+OO 6.75E+08 O.OOE+OO 6.36E+08 11 Se-75 O.OOE+OO 2.65E+08 1.03E+08 O.OOE+OO 3.85E+08 O.OOE+OO 3.83E+07 12 Rb-86 O.OOE+OO 2.19E+08

1. 02E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.33E+07 13 Sr-89 9.97E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 14 Sr-90 6.05E+ll O.OOE+OO 1.48E+ll O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+10 15 Y-91 5.11E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+09 15 Zr-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+OO 5.91E+05 O.OOE+OO

1. 19E+09 17 Nb-95

1. 42E+05 7.92E+04 4.26E+04 O.OOE+OO 7.83E+04 O.OOE+OO 4.81E+08 18 Nb-97 2.16E-06 5.46E-07

1. 99E-07 O.OOE+OO 6.37E-07 O.OOE+OO 2.02E-03 19 Mo-99 O.OOE+OO 6.15E+06

1. 17E+06 O.OOE+OO 1.39E+07 O.OOE+OO

1. 43E+07 20 Tc-99m 3.lOE+OO 8.77E+OO 1.12E+02 O.OOE+OO 1.33E+02 4.30E+OO 5.19E+03 21 Ru-103 4.77E+06 O.OOE+OO 2.06E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E+08 22 Ru-106 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+l0 23 Ag-llOm 1.05E+07 9.75E+06 5.79E+06 0.00E+OO 1.92E+07 O.OOE+OO 3.98E+09 24 Sb-124 1.04E+08 1.96E+06 4.11E+07 2.51E+05 O.OOE+OO 8.07E+07 2.94E+09 25 Sb-125

1. 37E+08 1.53E+06 3.25E+07 1.39E+05 O.OOE+OO

1. 05E+08 1.50E+09 26 Sb-126 7.01E+06

1. 43E+05 2.53E+06 4.29E+04 O.OOE+OO 4.30E+06 5.73E+08 27 Te-127m 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 O.OOE+OO

1. 17E+09 28 Te-129m 2.51E+08 9.38E+07 3.98E+07 8.64E+07 1.05E+09 0.00E+OO 1.27E+09 29 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+l0 1.98E+08 O.OOE+OO 3.05E+07 30 I-133 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 O.OOE+OO 3.26E+06 31 Cs-134 4.67E+09

1. llE+lO 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 32 Cs-136 4.27E+07 1.69E+08 1.21E+08 O.OOE+OO 9.38E+07 l.29E+07

1. 91E+07 33 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+OB 34 Ba-140 1.29E+08 1.61E+05 8.42E+06 O.OOE+OO 5.49E+04.

9.24E+04 2.65E+08 35 La-140

1. 98E+03 9.97E+02 2.63E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07

\\

36 Ce-141 1.97E+05 l.33E+05 1.51E+04 O.OOE+OO 6.19E+04 O.OOE+OO 5.10E+08 37 Ce-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+OO

1. llE+lO All nuclidea (except H-3 and C-14) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station ProccdureNUI!lbtt:

l/2-0DC-2.02 Yrtle:

Unit Level OfUae:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS R.evi&ion:

Pago Number:

11 98 of 1~1 ATTACHMENT J Page 7 of 19 P&I ORGAN DOSE FACTORS Table 2.3-8 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway - Vegetation Age Group -

Teen Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2

C-14 1.45E+06 2.91E+05 2.91E+0S 2.91E+05 2.91E+05 2.91E+05 2.91E+05 3

P-32 1.61E+09 9.98E+07 6.24E+07 0.O0E+00 0.00E+00 0.00E+00 1.35E+08 4

Cr-51 0.00E+00 0.00E+OO 6.17E+04 3,43E+04 1.35E+04

8. 81E+04

1. 04E+07 5

Mn-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 6

Fe-59

1. 79E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.90E+08 7

Co-57 0.00E+00 1.79E+07 3.00E+07 0.00E+00 0.00E+00 0.00E+O0 3.33E+08 8

Co-58 0.00E+00 4.36E+07 1.00E+08 0.00E+00 O.00E+00 0.00E+00 6.01E+08 9

Co-60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 10 Zn-65 4.24E+08 1.47E+09 6.87E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 16 Se-75 0.00E+00 4.16E+08 1.63E+08 0.00E+00 6.12E+08 0.00E+00 4.25E+07 11 Rb-86 0.00E+00 2.74E+08

1. 29E+08 0.00E+00 0.00E+00 0.00E+00 4.05E+07 12 Sr-89

1. 51E+l0 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00

1. 80E+09 13 Sr-90 7.51E+ll 0.00E+00 1.85E+ll 0.00E+00 0.00E+00 0.00E+00

2. llE+l0 14 Y-91 7.84E+06 O.00E+0O 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.21E+09 15 Zr-95

1. 72E+06 5.43E+05

3. 74E+05 0.00E+00 7.98E+05 0.00E+00

1. 25E+09 17 Nb-95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 18 Nb-97 2.00E-06 4.97E-07

1. 81E-07 0.00E+00 5.81E-07 0.00E+00

1. 19E-02 19 Mo-99 0.00E+00 5.65E+06

1. 08E+06 0.00E+00

1. 29E+07 0.00E+00 1.01E+07 20 Tc-99m 2.74E+00

7. 64E+0O 9.90E+0l 0.00E+00 1.14E+02 4,24E+00 5.02E+03 21 Ru-103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 22 Ru-106 2.38E+08 0.00E+0O 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 23 Ag-ll0m 1.52E+07 1.43E+07

8. 72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 24 Sb-124

1. 54E+08 2.84E+06 6.02E+07 3.S0E+0S 0.00E+00 1.35E+08 3.11E+09 25 Sb-125 2.14E+08 2.34E+06 5.01E+07 2.05E+05 O.00E+O0

1. 88E+08 1.67E+09 26 Sb-126 7.37E+06 1.51E+05 2.65E+06 4.17E+04 0.00E+00 5.28E+06 4.36E+08 27 Te-127m 5.52E+08 1.96E+08 6.56E+07

1. 31E+08 2.24E+09 0.00E+00 l,37E+09 28 Te-129m 3.62E+08 1.34E+08 5.73E+07

1. l 7E+08

1. 51E+09 0.00E+00 1.36E+09 29 I-131 7.69E+07

1. 08E+08 5.78E+07 3.14E+10

1. 85E+08 0.00E+00 2.13E+07 30 I-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 31 Cs-134 7.10E+09

1. 67E+l0 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 32 Cs-136 4.38E+07

1. 72E+08 1.16E+08 0.0OE+00 9,37E+07 1.48E+07

1. 39E+07 33 Cs-137 1.0lE+l0

1. 35E+l0 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 34 Ba-140

1. 38E+08 1.69E+05 8.90E+06 0.0OE+00 5,74E+04 1.14E+05 2.13E+08 35 La-140 1.81E+03 8.88E+02 2.36E+02 0.0OE+00 0.00E+00 0.00E+00 5.10E+07 36 Ce-141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 37 Ce-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 O.00E+00

1. 33E+10 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02 Titlo:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision; Page Number:

11 99 of 131 ATTACIIMENT J Page 8 of 19 P&I ORGAN DOSE FACTORS Table 2.3-9 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway -

Vegetation Age Group ~ Child Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4,. 01E+03 2

C-14 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. 5BE+OB l.30E+OB O.OOE+OO O.OOE+OO O.OOE+OO 9.32E+07 4 Cr-51 O.OOE+OO O.OOE+OO l.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 5

Mn-54 O.OOE+OO 6.65E+OB 1.77E+OB O.OOE+OO 1.86E+OB O.OOE+OO 5.58E+OB 6 Fe-59 3.9BE+OB 6.43E+OB 3.20E+OB O.OOE+OO O.OOE+OO 1.87E+OB 6.70E+OB 7 Co-57

0. OOE,+00 2.99E+07 6.04E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+OB 8

Co-58 O.OOE+OO 6.44E+07

1. 97E+OB O.OOE+OO '

O.OOE+OO O.OOE+OO 3.76E+OB 9 Co-60 O.OOE+OO 3.7BE+OB 1.12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 10 Zn-65 B.13E+OB 2.17E+09 1.35E+09 O.OOE+OO

1. 36E+09 O.OOE+OO 3.BOE+OB 16 Se-75 O.OOE+OO 7.5BE+OB 3.92E+OB O.OOE+OO l.03E+09 O.OOE+OO 3.51E+07 11 Rb-86 O.OOE+OO 4.52E+OB 2.78E+OB O.OOE+OO O.OOE+OO O.OOE+OO 2.91E+07 12 Sr-89 3.60E+10 O.OOE+OO

1. 03E+09 O.OOE+OO O.OOE+OO O.OOE+OO

1. 39E+09 13 Sr-90

1. 24E+l2 O.OOE+OO 3.15E+ll O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 14 Y-91 1.86E+07 O.OOE+OO 4.99E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+09 15 Zr-95 3.86E+06 B.4BE+05 7.55E+05 O.OOE+OO l.21E+06 O.OOE+OO 8.85E+OB 17 Nb-95 4.11E+05 l.60E+05 1.14E+05 O.OOE+OO l.50E+05 O.OOE+OO 2.96E+OB 18 Nb-97 3.65E-06 6.59E-07 3.0BE-07 O.OOE+OO 7.31E-07 O.OOE+OO 2.03E-01 19 Mo-99 O.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 O.OOE+OO 5.90E+06 O.OOE+OO 3.86E+07 O.OOE+OO 3.97E+08 22 Ru-106 7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO l.01E+09 O.OOE+OO 1.16E+10 23 Ag-llOm 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+OB 4.57E+06 1.23E+OB 7.77E+05 O.OOE+OO 1.95E+OB 2.20E+09 25 Sb-125 4.99E+OB 3.85E+06 1.05E+OB 4.63E+05 O.OOE+OO 2.78E+OB l.19E+09 26 Sb-126 1.39E+07 2.12E+05 4.9BE+06 B.13E+04 O.OOE+OO 6.62E+06 2.BOE+OB 27 Te-127m 1.32E+09 3.56E+OB 1.57E+OB 3.16E+OB 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 l.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+l0 2.63E+l0 5.55E+09 O.OOE+OO 8.15E+09 2.93E+09 l.42E+OB 32 Cs-136 8.24E+07 2.27E+08 1.47E+08 O.OOE+OO

1. 21E+OB 1.80E+07 7.96E+06 33 Cs-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+OB 34 Ba-140 2.77E+OB 2.42E+07

1. 62E+07 O.OOE+OO 7.89E+04

1. 45E+05 1.40E+OB 35 La-140 3.25E+03 1.13E+03 3.83E+02 O.OOE+OO O.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+OB 3.98E+07 6.78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02

Title:

Unit 1/2 ODCM: GASEOUS EFFLUENTS Revision:

11 Pathway -

Meat Age Group - Adult Nuclide 1

H-3 2 C-14 3

P-32 4 Cr-51 5

Mn-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 Nb-97 19 Mo-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-llOm 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127m 28 Te-129m 29 I-131 30 I-133 31 Ca-134 32 Ca-136 33 Cs-137 34 Ba-140 35 La-140 36 Ce-141 37 Ce-144 Bone 0.00E+OO 3.33E+05 3.95E+09 O.OOE+OO O.OOE+OO 2.14E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.54E+08 O.OOE+OO O.OOE+OO 2.41E+08 8.41E+09 8.94E+05 l.47E+06 l.89E+06

5. 32E-119 O.OOE+OO 3.83E-21 8.57E+07 l.97E+09 4.77E+06 O.OOE+OO O.OOE+OO 0.00E+OO 8.38E+08 9.33E+08 9.13E+06 3.12E-Ol 4.53E+08 l.02E+07 5.90E+08 2.44E+07 3.16E-02 l.16E+04

1. 03E+06 ATTACHMENT J Page 9 of 19 P&I ORGAN DOSE FACTORS Table 2.3-10 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/aec)

Liver 3.25E+02 6.66E+04 2.46E+08 O.OOE+OO 6.49E+06 5.04E+08 4.01E+06 1.42E+07 5.12E+07 8.09E+08 l.21E+08 4.11E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+05 l.05E+06 l.34E-119 8.51E+04 l.08E-20 O.OOE+OO O.OOE+OO 4.41E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.00E+08 3.48E+08 l.31E+07 5.42E-Ol l.08E+09 4.04E+07 8.06E+08 3.06E+04 l.59E-02 7.83E+03 4.32E+05 T. Body 3.25E+02 6.66E+04 l.53E+08 5.86E+03 l.24E+06

1. 93E+08 6, 66E+o6 3.18E+07 l.13E+08 3.66E+08 4.70E+07 l.92E+08 6.92E+06 2.06E+09 2.39E+04 3.19E+05 5.64E+05 4.91E-120 l.62E+04 l.38E-19 3.69E+07 2.49E+08 2.62E+06 O.OOE+OO O.OOE+OO O.OOE+OO

1. 02E+08 l.48E+08 7.48E+06 l.65E-01 8.81E+08 2.91E+07 5.28E+08 l.60E+06 4.21E-03 8.88E+02 5.55E+04 Thyroid Kidney 3.25E+02 3.25E+02 6.66E+04 6.66E+04 O.OOE+OO O.OOE+OO 3.50E+03 l.29E+03 O.OOE+OO l.93E+06 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 5.41E+08 O.OOE+OO l.76E+08 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 7.39E+05 O.OOE+OO l.04E+06 O.OOE+OO l.57E-119 O.OOE+OO l.93E+05 O.OOE+OO l.64E-19 O.OOE+OO 3.27E+08 O.OOE+OO 3.80E+09 O.OOE+OO 8.67E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.14E+08 3.40E+09 3.21E+08 3.89E+09 4.28E+09 2.24E+07 7.96E+Ol 9.46E-Ol O.OOE+OO 3.49E+08 O.OOE+OO 2.25E+07 O.OOE+OO 2.74E+08 O.OOE+OO l.04E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.64E+03 O.OOE+OO 2.56E+05 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30 C-14 calculated per ERS-LMR-001 Level Of Use:

General Skill Reference Page Number:

100 nf' n 1 Lung 3.25E+02 6.66E+04 O.OOE+OO 7.78E+03 O.OOE+OO l.41E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-21 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 O.OOE+OO l.16E+08 3.08E+06 9.10E+07 l.75E+04 O.OOE+OO O.OOE+OO O.OOE+OO GI-LLI 3.25E+02 6.66E+04 4.44E+08 l.47E+06

1. 99E+07 1.68E+09 l.02E+08 2.87E+08 9.61E+08 5.10E+08 l.75E+07 8.11E+07 3.87E+07 2.43E+08 4.92E+08 l.49E+09 6.37E+09

4. 96E-116 l.97E+05 6.40E-18 l.OOE+lO l.27E+ll 1.80E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+09 4.70E+09 3.45E+06 4.87E-01 l.89E+07 4.59E+06 l.56E+07 5.02E+07 l.17E+03 2.99E+07 3.50E+08

Beaver Valley Power Station

Title:

ODCM: GASEOUS EFFLUENTS Pathway= Meat Age Group -

Teen Nuclide 1

H-3 2

C-14 3

P-32 4 Cr-51 5

Mn-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 Nb-97 19 Mo-99 20 Tc-99rn 21 Ru-103 22 Ru-106 23 Ag-llOrn 24 Sb-124 25 Sb-125 26 Sb-126 27 Te-127rn 28 Te-129rn 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 2.81E+05 3.34E+09 O.OOE+OO O.OOE+OO l.71E+08 O.OOE+OO O.OOE+OO O.OOE+OO l.79E+08 O.OOE+OO O.OOE+OO 2.03E+08 5.44E+09 7.53E+05 l.18E+06 l.47E+06

4. 44E-119 O.OOE+OO 3.04E-21 6.98E+07 l.28E+09 3.61E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.07E+08 7.82E+08 7.59E+06 2.61E-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 OOSE FACTORS Table 2.3-11 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Liver T. Body l.94E+02 l.94E+02 5.62E+04 5.62E+04 2.07E+08 l.29E+08 O.OOE+OO 4.69E+03 4.95E+06 9.81E+05 4.00E+08 l.54E+08 3.22E+06 5.40E+06 l.09E+07 2.52E+07 3.97E+07 8.95E+07 6.21E+08 2.90E+08 l.01E+08 3.98E+07 3.43E+08 l.61E+OB O.OOE+OO 5.83E+06 O.OOE+OO l.34E+09 O.OOE+OO 2.02E+04 3.71E+05 2.55E+05 8.17E+05 4.50E+05 l.lOE-119 4.02E-120 7.03E+04 l.34E+04 8.48E-21 l.lOE-19 O.OOE+OO 2.98E+07 0.00E+OO 2.09E+OB

3. 42E+06

2. 08E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.51E+08 8.41E+07 2.90E+08 l.24E+08 l.06E+07 5.71E+06 4.42E-Ol l.35E-01 8.48E+08 3.93E+08 3.14E+07 2.11E+07 6.51E+08 2.27E+08 2.47E+04 l.30E+06 l.28E-02 3.40E-03 6.49E+03 7.46E+02 3.61E+05 4.6BE+04 Thyroid l.94E+02 5.62E+04 O.OOE+OO 2.60E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.ODE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.ODE+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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.68E+08 2.52E+08 3.10E+09 6.17E+Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Procedmc Number:

l/2-0DC-2.02 Unit 1/2 R.evisioo:

11 Kidney l.94E+02 5.62E+04 O.OOE+OO l.03E+03 1.4BE+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.97E+08 l.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.45E+05 7.92E+05 l.29E-119 l.61E+05

1. 26E-19 2.46E+08 3.19E+09 6.52E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+09 3.27E+09 l.83E+07 7.75E-Ol 2.69E+08 l.71E+07 2.22E+08 8.38E+03 O.OOE+OO 3.06E+03 2.15E+05 Level OfUae:

General Skill Reference Page Number:

101 ofHl Lung l.94E+02 5.62E+04 O.OOE+OO 6.69E+03 O.OOE+OO l.26E+08 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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. 71E-21 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 O.OOE+OO l.03E+08 2.69E+06 8.61E+07

1. 66E+04 O.OOE+OO O.OOE+OO O.OOE+OO GI-LLI l.94E+02 5.62E+04 2.80E+08 7.88E+05 l.01E+07 9.45E+08 6.01E+07

1. 51E+08 5.17E+08 2.63E+08 l.03E+07 5.08E+07 2.42E+07 l.53E+08 3.09E+08 8.56E+08 3.49E+09 2.63E-115 l.26E+05 5.57E-18 5.83E+09

7. 94E+l0 9.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO l.76E+09 2.93E+09 2.10E+06 3.34E-Ol l.05E+07 2.53E+06 9.27E+06 3.11E+07 7.33E+02 l.86E+07 2.19E+08 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Proccdurc Number:

l/2-0DC-2.02

Title:

Unit Level OfUse:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number.

11 101 of Bl ATTACHMENT J Page 11 of 19 P&I ORGAN DOSE FACTORS Table 2.3-12 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway= Meat Age Group ~ Child Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2

C-14 5.29E+05

1. 06E+05 l.06E+05 1.06E+05 1.06E+05

1. 06E+05 1.06E+05 3

P-32 6.29E+09 2.94E+OB 2.43E+OB O.OOE+OO O.OOE+OO O.OOE+OO 1.74E+OB 4 Cr-51 O.OOE+OO O.OOE+OO 7.31E+03 4.06E+03 1.11E+03 7.41E+03 3.BBE+05 5

Mn-54 O.OOE+OO 5.66E+06 1.51E+06 O.OOE+OO l.59E+06 O.OOE+OO 4.75E+06 6 Fe-59 3.04E+OB 4.91E+OB 2.45E+OB O.OOE+OO O.OOE+OO

1. 42E+OB 5.12E+OB 7

Co-57 O.OOE+OO 4.21E+06 8.52E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.45E+07 8

Co-58 O.OOE+OO 1.28E+07 3.91E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.45E+07 9 Co-60 O.OOE+OO

4. 72E+07 1.39E+OB O.OOE+OO O.OOE+OO O.OOE+OO 2.61E+OB 10 Zn-65 2.68E+OB 7.15E+OB 4.44E+0B O.OOE+OO 4.50E+OB O.OOE+OO

1. 25E+OB 11 Se-75 I

O.OOE+OO 1.45E+OB 7.49E+07 O.OOE+OO 1.96E+OB O.OOE+OO 6.72E+06 12 Rb-86 I

O.OOE+OO 4.87E+OB 2.99E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.13E+07 13 Sr-89 3.85E+08 O.OOE+OO 1.10E+07 O.OOE+OO O.OOE+OO O.OOE+OO

1. 49E+07 14 Sr-90 7.03E+09 O.OOE+OO 1.78E+09 O.OOE+OO O.OOE+OO O.OOE+OO 9.47E+07 15 Y-91 l.42E+06 O.OOE+OO 3.81E+04 O.OOE+OO O.OOE+OO O.OOE+OO

1. 90E+08 16 Zr-95 2.09E+06 4.59E+05 4.09E+05 O.OOE+OO 6.57E+05 O.OOE+OO 4.79E+08 17 Nb-95 2.54E+06 9.90E+05 7.07E+05 O.OOE+OO 9.30E+05 O.OOE+OO

1. 83E+09 18 Nb-97 8.24E-119 1.49E-119 6.95E-120 O.OOE+OO

1. 65E-119 O.OOE+OO 4.59E-114 19 Mo-99 O.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 O.OOE+OO 1.52E-19 5.31E-21 5.95E-18 21 Ru-103 1.26E+08 O.OOE+OO 4.85E+07 O.OOE+OO 3.18E+08 O.OOE+OO 3.26E+09 22 Ru-106 3.12E+09 O.OOE+OO 3.89E+08 O.OOE+OO 4.21E+09 O.OOE+OO 4.85E+l0 23 Ag-llOm 5.99E+06 4.04E+06 3.23E+06 O.OOE+OO 7.53E+06 O.OOE+OO 4.81E+08 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m 1.33E+09 3.59E+08 1.58E+08 3.19E+08 3.80E+09 O.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 I-131

1. 41E+07 1.42E+07 8.04E+06 4.68E+09 2.32E+07 O.OOE+OO 1.26E+06 30 I-133 4.84E-01 5.99E-01 2.27E-01 1.11E+02 9.98E-Ol O.OOE+OO 2.41E-01 31 Cs-134 6.35E+08 1.04E+09 2.20E+08 O.OOE+OO 3.23E+08 l.16E+08 5.62E+06 32 Cs-136 1.38E+07 3.78E+07 2.45E+07 O.OOE+OO 2.01E+07 3.00E+06 1.33E+06 33 Cs-137 9.02E+08 8.63E+08

1. 27E+08 0.00E+OO 2.81E+08 1.01E+08 5.40E+06 34 Ba-140

3. 72E+07 3.26E+06 2.17E+06 O.OOE+OO

1. 06E+04 1.94E+04 1.89E+07 35 La-140 4.76E-02

1. 66E-02 5.61E-03 O.OOE+OO O.OOE+OO O.OOE+OO 4.63E+02 36 Ce-141 1.83E+04 9.13E+03 1.36E+04 O.OOE+OO 4.00E+03 O.OOE+OO 1.14E+07 37 Ce-144 1.64E+06 5.15E+05

8. 77E+04 O.OOE+OO 2.85E+05 O.OOE+OO 1.34E+08 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number.

l/2-0DC-2.02 Trtlc:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revwon:

11 Page Number:

101 of Bl ATTACHMENT J Page 12 of 19 P&I ORGAN DOSE FACTORS Table 2.3-13 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway= Cow Milk Age Group = Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.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 O.OOE+OO O.OOE+OO O.OOE+OO 1.63E+09 4 Cr-51 O.OOE+OO O.OOE+OO 2.38E+04 1.42E+04 5.24E+03 3.15E+04 5.98E+06 5 Mn-54 O.OOE+OO 5.95E+06 1.13E+06 O.OOE+OO

1. 77E+06 O.OOE+OO 1.82E+07 6 Fe-59 2.40E+07 5.63E+07 2.16E+07 O.OOE+OO O.OOE+OO 1.57E+07 1.88E+08 7 Co-57 O.OOE+OO 9.10E+05 1.51E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.31E+07 8 Go-58 O.OOE+OO 3.67E+06 8.22E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.43E+07 9 Co-60 O.OOE+OO l.12E+07 2.46E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+08 10 Zn-65 9.80E+08 3.12E+09 1.41E+09 O.OOE+OO 2.09E+09 O.OOE+OO 1.96E+09 11 Se-75 O.OOE+OO 1.14E+09 4.41E+08 O.OOE+OO 1.65E+09 O.OOE+OO

1. 64E+08 12 Rb-86 O.OOE+OO 2.19E+09 1.02E+09 O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+08 13 Sr-89 l.16E+09 O.OOE+OO 3.33E+07 O.OOE+OO O.OOE+OO O.OOE+OO

1. 86E+08 14 Sr-90 3.16E+l0 O.OOE+OO 7.76E+09 O.OOE+OO O.OOE+OO O.OOE+OO 9.14E+08 15 Y-91 6.78E+03 O.OOE+OO 1.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.73E+06 16 Zr-95 7.40E+02 2.37E+02 1.61E+02 O.OOE+OO 3.72E+02 O.OOE+OO 7.52E+05 17 Nb-95 6.77E+04 3.77E+04 2.03E+04 O.OOE+OO

3. 72E+04 O.OOE+OO 2.29E+08 18 Nb-97 2.BlE-12

7. llE-13 2.60E-13 O.OOE+OO 8.30E-13 O.OOE+OO 2.62E-09 19 Mo-99 O.OOE+OO 2.11E+07 4.01E+06 O.OOE+OO 4.77E+07 O.OOE+OO 4.88E+07 20 Tc-99rn 2.83E+OO 7.99E+OO 1.02E+02 O.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 O.OOE+OO 9.68E+04 22 Ru-106

1. 43E+04 O.OOE+OO 1.81E+03 O.OOE+OO 2.77E+04 O.OOE+OO 9.27E+05 23 Ag-llOm 4.16E+07 3.84E+07 2.28E+07 O.OOE+OO 7.56E+07 O.OOE+OO 1.57E+l0 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.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+08 1.18E+ll 6.17E+08 O.OOE+OO 9.50E+07 30 I-133 3.29E+06 5.72E+06

1. 75E+06 8.41E+08 9.99E+06 O.OOE+OO 5.14E+06 31 Cs-134 3.89E+09 9.27E+09 7.58E+09 O.OOE+OO 3.00E+09 9.96E+08 1.62E+08 32 Cs-136 2.23E+08 8.82E+08 6.35E+08 O.OOE+OO 4.91E+08 6.73E+07 1.00E+08 33 Cs-137 4.99E+09 6.82E+09 4.47E+09 O.OOE+OO 2.32E+09 7.70E+08 1.32E+08 34 Ba-140 2.28E+07 2.87E+04 1.49E+06 O.OOE+OO 9.74E+03 1.64E+04 4.70E+07 35 La-140 3.84E+OO 1.93E+OO

5. llE-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+05 36 Ce-141 3.99E+03 2.70E+03 3.06E+02 O.OOE+OO

1. 25E+03 O.OOE+OO l.03E+07 37 Ce-144 2.54E+05 1.06E+05 1.36E+04 O.OOE+OO 6.29E+04 O.OOE+OO 8.58E+07 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-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 10A. nfl31 ATTACHMENT J Page 13 of 19 P&I ORGAN DOSE FACTORS Table 2. 3-14 R VALUES FOR BEAVER VALLEY SITE (sq meter-=em/yr per uCi/aec)

Pathway -

Cow Milk Age Group = Teen Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 0.00E+00 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 2

C-14 6.70E+05 l.34E+05 1.34E+05 1.34E+05 l.34E+05 1.34E+05

1. 34E+05 3

P-32

2. 67E+10 1.66E+09 1.04E+09 0.00E+00 0.00E+OO 0.0OE+00 2.25E+09 4

Cr-51 0.00E+O0 0.0OE+00 4.15E+04 2.31E+04 9.10E+03 5.93E+04 6.97E+06 5

Mn-54 0.00E+00 9.91E+06 1.96E+06 0.00E+00 2.95E+06 0.00E+00 2.03E+07 6 Fe-59 4.18E+07 9.76E+07 3.77E+07 0.00E+00 0.00E+O0 3.08E+07 2.31E+08 7

Co-57 0.00E+00 1.60E+06 2.68E+06 0.00E+00 0.00E+00 0.00E+00 2.98E+07 8 Co-58 0.00E+00 6.17E+06

1. 42E+07 O.00E+00 0.00E+00 0.00E+00 8.51E+07 9 Co-60 0.O0E+O0 1.89E+07 4.26E+07 0.00E+00 0.00E+O0 0.OOE+00 2.46E+08 10 Zn-65 1.51E+09 5.23E+09 2.44E+09 0.00E+00 3.34E+09 0.00E+00 2.21E+09 11 Se-75 0.00E+O0 2.0BE+09 8.lSE+0B 0.00E+00 3.0SE+09 0.00E+0O 2.12E+08 12 Rb-86 0.00E+00 3.99E+09

1. 87E+o9 O.00E+00 0.00E+00 0.00E+00 5.91E+08 13 Sr-89 2.14E+09 O.00E+00 6.12E+07 0.00E+00 0.00E+O0 O.0OE+00 2.55E+08 14 Sr-90 4.47E+10 0.00E+00 1.l0E+l0 0.00E+00 0.00E+O0 0.00E+00 1.25E+09 15 Y-91 l.25E+04 0.00E+00 3.35E+02 O.00E+00 0.00E+00 0.00E+00 5.11E+06 16 Zr-95 1.29E+03 4.08E+02 2.81E+02 0.00E+00 6.00E+02 0.00E+00 9.42E+05 17 Nb-95 l.16E+05 6.41E+04 3.53E+04 0.00E+00 6.21E+04 0.00E+00 2.74E+08 18 Nb-97 5.13E-12 1.27E-12 4.65E-13 0.00E+00 1.49E-12 O.00E+00 3.04E-08 19 Mo-99 0.O0E+O0 3.80E+07 7.25E+06 0.00E+00 8.70E+07 0.00E+O0 6.81E+07 20 Tc-99m 4.90E+00 1.37E+0l 1.77E+02 0.00E+00 2.04E+02 7.59E+00 8.98E+03 21 Ru-103 l.47E+03 0.00E+00 6.30E+02 0.00E+00 5.20E+03 0.00E+O0 l.23E+05 22 Ru-106 2.03E+04 0.00E+0O 3.32E+03 0.00E+00 5.08E+04 0.00E+00

1. 26E+06 23 Ag-ll0rn 6.87E+07 6.50E+07 3.95E+07 0.00E+00 l.24E+08 O.00E+00

1. 83E+10 24 Sb-124 0.00E+O0 0.0OE+0O O.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 25 Sb-125 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+O0 0.00E+00 0.00E+00 26 Sb-126 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+O0 0.00E+00 0.00E+0O 27 Te-127m 6.34E+07 2.25E+07 7.54E+06 1.51E+07 2.57E+08 0.00E+00 1.58E+08 28 Te-129m 9.06E+07 3.36E+07 1.43E+07 2.92E+07 3.79E+08 O.O0E+O0 3.40E+08 29 I-131 4.57E+08 6.39E+0B 3.43E+0B

1. 87E+ll l.10E+09 O.00E+00

1. 26E+0B 30 I-133 6.01E+06 1.02E+07 3.11E+06 1.42E+09

1. 79E+07 0.00E+00

7. 71E+06 31 Cs-134 6.76E+09 1.59E+10 7.38E+09 0.00E+00 5.06E+09 1.93E+09 1.98E+08 32 Cs-136 3.B0E+08 1.50E+09 1.01E+09 0.00E+00 8.lSE+0B l.28E+08 1.20E+0B 33 Cs-137 9.05E+09 1.20E+l0 4.19E+09 0.00E+00 4.10E+09 1.59E+09

1. 71E+08 34 Ba-140 4.12E+07 5.05E+04 2.65E+06 0.00E+O0

1. 71E+04 3.39E+04 6.35E+07 35 La-140 6.89E+00 3.39E+00 9.0lE-01 0.00E+00 0.00E+00 0.00E+00 1.94E+05 36 Ce-141 7.32E+03 4.89E+03 5.62E+02 0.00E+00 2.30E+03 O.00E+00

1. 40E+07 37 Ce-144 4.67E+05 1.93E+05 2.51E+04 0.00E+00 1.15E+05 0.00E+00 l.17E+08 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number.

l/2-0DC-2.02

Title:

Unit:

1/2 Level OfUse:

General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

11 Page Number:

10" nf Bl ATTACHMENT J Page 14 of 19 P&I ORGAN DOSE FACTORS Table 2.3-15 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uci/sec)

Pathway -

Cow Milk Age Group~ Child Nuclide l

H-3 2

C-14 3

P-32 4 Cr-51 5

Mn-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 Nb-97 19 Mo-99 20 Tc-99m 21 Ru-103 22 Ru-106 23 Ag-llOm 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 Liver T. Body Thyroid Kidney Lung GI-LLI O.OOE+OO 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 l.65E+06 3,29E+05 3.29E+05 3.29E+05 3.29E+05 3,29E+05 3.29E+05 6.59E+l0 3.09E+09 2.54E+09 O.OOE+OO O.OOE+OO O.OOE+OO l.82E+09 O.OOE+OO O.OOE+OO 8.46E+04 4.70E+04 1.28E+04 8.58E+04 4.49E+06 O.OOE+OO l.48E+07 3.95E+06 O.OOE+OO 4.16E+06 O.OOE+OO l.24E+07 9.70E+07 1.57E+08 7.82E+07 O.OOE+OO O.OOE+OO 4.55E+07 l.63E+08 O.OOE+OO 2.73E+06 5.52E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.24E+07 O.OOE+OO 9.43E+06 2.89E+07 O.OOE+OO O.OOE+OO O.OOE+OO 5,50E+07 O.OOE+OO 2.94E+07 8.67E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.63E+08 2.95E+09 7.87E+09 4.89E+09 O.OOE+OO 4.96E+09 O.OOE+OO l.38E+09 O.OOE+OO 3.89E+09 2.01E+09 O.OOE+OO 5.26E+09 O.OOE+OO 1.80E+08 O.OOE+OO 7.40E+09 4.55E+09 O.OOE+OO O.OOE+OO O.OOE+OO 4.76E+08 5,29E+09 O.OOE+OO l.51E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.05E+08 7.55E+l0 O.OOE+OO l.91E+l0 O.OOE+OO O.OOE+OO O.OOE+OO l.02E+09 3.08E+04 O.OOE+OO 8,24E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.11E+06 3,00E+03 6.60E+02 5.88E+02 O.OOE+OO 9.45E+02 O.OOE+OO 6.89E+05 2.61E+05 l.02E+05 7.26E+04 O.OOE+OO 9.54E+04 O.OOE+OO l.88E+08 1.25E-11 2.25E-12 1.05E-12 O.OOE+OO 2.50E-12 O.OOE+OO 6.94E-07 O.OOE+OO 6.92E+07 l.71E+07 O.OOE+OO l.48E+08 O.OOE+OO 5.72E+07 1.12E+Ol 2.20E+Ol 3.65E+02 O.OOE+OO 3.20E+02 l.12E+Ol 1.25E+04 3.49E+03 O.OOE+OO l.34E+03 O.OOE+OO 8.78E+03 O.OOE+OO 9,01E+04 6.49E+04 O.OOE+OO 8.10E+03 O.OOE+OO 8.76E+04 O.OOE+OO 1.01E+06 1.49E+08 l.01E+08 8.05E+07 O.OOE+OO 1.87E+08 O.OOE+OO 1.20E+l0 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 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 O.OOE+OO O.OOE+OO O.OOE+OO

1. 56E+08 2.23E+08 l.11E+09

1. 4 6E+07 l.56E+10 8.58E+08 2.18E+l0 9.94E+07 l.65E+Ol l.80E+04 l.15E+06 4.21E+07 6.24E+07

1. 11E+09 1.81E+07 2.56E+l0 2.36E+09 2.09E+l0

8. 71E+o6 5.77E+OO 8.99E+03 3.61E+05 l.86E+07 3.47E+07 6.33E+08 6.83E+06 5.40E+09 l.53E+09 3.08E+09 5.80E+06 l.94E+OO

1. 34E+04 6.15E+04 3.74E+07 7.20E+07

3. 68E+ll 3.36E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.46E+08 6.56E+08 1.83E+09 3.01E+07 7.93E+09 l.26E+09 6.80E+09 2.84E+04 O.OOE+OO 3.94E+03 2.00E+05 O.OOE+OO O.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

1. 27E+08 2.72E+08 9.92E+07 7.28E+06

1. 38E+08 8.29E+07

1. 31E+08 5.04E+07 l.61E+05 l,12E+07 9.41E+07 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number.

l/2-0DC-2.02 Yrtle:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 toll nf 131 ATTACHMENT J Page 15 of 19 P&I ORGAN DOSE FACTORS Table 2.3-16 R VALOES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/aec)

Pathway~ Cow Milk Age Group= Infant Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 2.38E+03 2.3BE+03 2.38E+03 2.38E+03 2.38E+03 2.3BE+03 2

C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 3

P-32

1. 36E+ll 7.99E+09 5.27E+09 O.OOE+OO O.OOE+OO O.OOE+OO

1. 84E+09 4

Cr-51 O.OOE+OO O.OOE+OO l.34E+05 8.75E+04 l.91E+04 l.70E+05 3.91E+06 5

Mn-54 O.OOE+OO 2.76E+07 6.25E+06 O.OOE+OO

6. 11E+06 O.OOE+OO l.01E+07 6

Fe-59

1. BlE+OB 3.16E+08 l.25E+08 O.OOE+OO O.OOE+OO 9.35E+07 l.51E+08 7

Co-57 O.OOE+OO 6.36E+06 l.03E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E+07 8

Co-58 O.OOE+OO l.89E+07 4.70E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+07 9 Co-60 O.OOE+OO 6.00E+07

1. 42E+08 O.OOE+OO O.OOE+OO O.OOE+OO

1. 43E+08 10 Zn-65 3.97E+09 l.36E+l0 6.27E+09 O.OOE+OO 6.60E+09 O.OOE+OO l.15E+l0 11 Se-75 O.OOE+OO 9.61E+09 4.13E+09 O.OOE+OO 9.31E+09 O.OOE+OO

1. 79E+08 12 Rb-86 O.OOE+OO l.88E+l0 9.28E+09 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+08 13 Sr-89

1. OlE+lO O.OOE+OO 2.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E+08 14 Sr-90

8. 22E+l0 O.OOE+OO 2.09E+l0 O.OOE+OO O.OOE+OO O.OOE+OO l.03E+09 15 Y-91 5.79E+04 O.OOE+OO l.54E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.15E+06 16 Zr-95 5.33E+03

1. 30E+o3 9.22E+02 O.OOE+OO l.40E+03 O.OOE+OO 6.47E+05 17 Nb-95 4.87E+05 2.01E+05 l.16E+05 O.OOE+OO l.44E+05 O.OOE+OO l.69E+OB 18 Nb-97 2.63E-ll 5.62E-12 2.03E-12 O.OOE+OO 4.39E-12 O.OOE+OO l.77E-06 19 Mo-99 O.OOE+OO l.77E+08 3.45E+07 O.OOE+OO 2.64E+08 O.OOE+OO 5.83E+07 20 Tc-99m 2.34E+Ol 4.82E+Ol 6.21E+02 O.OOE+OO 5.19E+02 2.52E+Ol l.40E+04 21 Ru-103 7.06E+03 O.OOE+OO 2.36E+03 O.OOE+OO

1. 47E+04 O.OOE+OO 8.59E+04 22 Ru-106

1. 34E+05 O.OOE+OO l.67E+04 O.OOE+OO

1. 58E+05 O.OOE+OO

1. 01E+06 23 Ag-llOm 2.75E+OB 2.01E+08

1. 33E+OB O.OOE+OO 2.88E+08 O.OOE+OO

1. 04E+l0 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m 3.16E+08 l.05E+08 3.83E+07 9.14E+07 7.79E+08 O.OOE+OO l.28E+08 28 Te-129m 4.58E+08

1. 57E+08 7.06E+07 l.76E+08 l.15E+09 O.OOE+OO 2.74E+08 29 I-131 2.31E+09 2.72E+09 l.20E+09

8. 95E+ll 3.18E+09 O.OOE+OO 9.72E+07 30 I-133 3.08E+07 4.49E+07 l.31E+07 8.17E+09 5.28E+07 O.OOE+OO 7.60E+06 31 Ca-134

2. 51E+l0 4.69E+l0 4.73E+09 O.OOE+OO

1. 21E+l0 4.95E+09 l.27E+08 32 Cs-136

1. 68E+09 4.93E+09 l.84E+09 O.OOE+OO

1. 97E+09 4.02E+OB 7.49E+07 33 Cs-137 3.48E+l0 4.07E+l0 2.89E+09 O.OOE+OO l.09E+l0 4.43E+09 l.27E+08 34 Ba-140 2.0SE+08 2.05E+05 l.05E+07 O.OOE+OO 4.86E+04

1. 2 6E+05 5.02E+07 35 La-140 3.45E+Ol l.36E+Ol 3.SOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.60E+05 36 Ce-141 3.57E+04 2.18E+04 2.57E+03 O.OOE+OO 6.72E+03 O.OOE+OO 1.13E+07 37 Ce-144 l.65E+06 6.75E+05 9.25E+04 O.OOE+OO 2.73E+05 O.OOE+OO 9.47E+07 All nuclidea (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-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:

Pago Number:

11 107 of 131 ATTACHMENT J Page 16 of 19 P&I ORGAN DOSE FACTORS Table 2.3-17 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/vr per uCi/sec)

Pathway~ Goat Milk Age Group ~ Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1 H-3 0.O0E+O0 9.15E+0l 9.15E+0l 9.15E+0l 9.15E+0l 9.15E+0l 9.15E+0l 2

C-14 4.36E+04

8. 72E+03 8.72E+03

8. 72E+03 8.72E+03 8.72E+03

8. 72E+03 3

P-32 1.74E+09 1.08E+08

6. 72E+07 0.0OE+0O 0.0OE+00 0.00E+00

1. 96E+08 4 Cr-51 0.O0E+O0 0.00E+00 2.85E+03 1.70E+03 6.28E+02 3.78E+03 7.17E+05 5 Mn-54 0.OOE+00 7.14E+05

1. 36E+05 0.O0E+00 2.12E+05 O.00E+OO 2.19E+06 6 Fe-59 2.88E+06 6.76E+06 2.59E+06 0.0OE+O0 0.0OE+00 1.89E+06 2.25E+07 7 Co-57 0.O0E+O0 1.09E+05 1.82E+05 0.00E+00 O.00E+00 0.00E+O0 2.77E+06 8 Co-58 O.OOE+00 4.40E+05 9.86E+05 0.O0E+00 0.0OE+00 0.00E+00 8.91E+06 9 Co-60 0.00E+00 1.34E+06 2.96E+06 0.00E+00 0.0OE+00 0.00E+00 2.52E+07 10 Zn-65 1.18E+08 3.74E+08

1. 69E+08 0.00E+00 2.50E+08 0.O0E+OO 2.36E+08 11 Se-75 0.OOE+O0 1.36E+08 5.29E+07 O.00E+O0

1. 98E+08 O.00E+00 1.97E+07 12 Rb-86 0.O0E+00 2.63E+08

1. 22E+08 0.00E+O0 0.00E+00 0.00E+0O 5.18E+07 13 Sr-89 1.39E+08 0.00E+00 3.99E+06 0.00E+00 0.0OE+O0 0.00E+0O 2.23E+07 14 Sr-90 3.80E+09 0.0OE+00 9.32E+08 0.00E+00 0.0OE+00 0.00E+00 1.10E+08 15 Y-91 8.14E+02 O.0OE+00 2.18E+0l 0.00E+0O 0.0OE+00 0.0OE+00 4.48E+05 16 Zr-95 8.87E+0l 2.BSE+0l 1.93E+0l 0.O0E+00 4.47E+Ol O.O0E+OO 9.02E+04 17 Nb-95 8.13E+03 4.52E+03 2.43E+03 0.00E+00 4.47E+03 0.00E+00 2.74E+07 18 Nb-97 3.38E-13 8.54E-14 3.12E-14 0.00E+OO 9.96E-14 0.0OE+00 3.15E-10 19 Mo-99 0.0OE+0O 2.53E+06 4.81E+05 0.00E+00

5. 72E+06 O.0OE+00 5.86E+06 20 Tc-99m 3.39E-01 9.59E-01

1. 22E+0l O.00E+00

1. 46E+0l 4.70E-01 5.67E+02 21 Ru-103 9.95E+0l O.0OE+00 4.29E+Ol 0.00E+OO 3.80E+02 0.0OE+O0 1.16E+04 22 Ru-106

1. 72E+03 0.0OE+00 2.18E+02 0.00E+00 3.32E+03 0.OOE+O0 1.llE+0S 23 Ag-ll0m 4.99E+06 4.61E+06 2.74E+06 0.O0E+00 9.07E+06 O.O0E+O0 1.88E+09 24 Sb-124 0.00E+00 0.0OE+00 0.00E+00

, 0.00E+00 0.00E+00 0.00E+00 0.00E+00 25 Sb-125 0.OOE+00 0.00E+00 0.00E+00 0.00E+O0 0.00E+O0 0.0OE+00 0.00E+00 26 Sb-126 0.0OE+0O 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.O0E+O0 0.00E+0O 27 Te-127m 4.13E+06

1. 48E+06 5.03E+05

1. 05E+06 1.68E+07 0.O0E+00

1. 38E+07 28 Te-129m 5.94E+06 2.22E+06 9.41E+05 2.04E+06 2.48E+07 0.O0E+00 2.99E+07 29 I-131 3.02E+07 4.32E+07 2.48E+07

1. 42E+10 7.40E+07 0.0OE+00 1.14E+07 30 I-133 3.95E+05 6.87E+05 2.09E+05

1. 01E+08 1.20E+06 0.OOE+00 6.17E+05 31 Cs-134 4.67E+08 1.11E+09 9.09E+08 0.00E+00 3.60E+08 l.19E+08 1.95E+07 32 Cs-136 2.68E+07

1. 06E+08 7.62E+07 0.00E+O0 5.89E+07 8.07E+06 1.20E+07 33 Cs-137 5.99E+08 8.19E+08 5.36E+08 0.00E+O0 2.78E+08 9.24E+07 1.59E+07 34 Ba-140 2.74E+06 3.44E+03 1.79E+05 0.00E+00 1.17E+03 1.97E+03 5.64E+06 35 La-140 4.60E-01 2.32E-01 6.13E-02 0.00E+00 O.0OE+00 0.00E+00 1.70E+04 36 Ce-141 4.79E+02 3.24E+02 3.68E+0l 0.00E+00 1.51E+02 0.O0E+00

1. 24E+06 37 Ce-144 3.05E+04 1.27E+04 1.64E+03 0.00E+00 7.55E+03 0.00E+O0 1.03E+07 All nuclides (except R-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-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 Revmon:

Page Number:

11 10R nf" 111 ATTACHMENT J Page 17 of 19 P&I ORGAN DOSE FACTORS Table 2.3-18 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/vr per uCi/sec)

Pathway a Goat Milk Age Group -

Teen Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO 1.19E+02 1.19E+02 l.19E+02 1.19E+02 l.19E+02 1.19E+02 2

C-14 8.04E+04

1. 61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 l.61E+04 3

P-32 3.21E+09

1. 99E+08

1. 24E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E+08 4

Cr-51 O.OOE+OO O.OOE+OO 4.98E+03 2.77E+03 1.09E+03 7.11E+03 8.37E+05 5

Mn-54 O.OOE+OO 1.19E+06 2.36E+05 O.OOE+OO 3.55E+05 O.OOE+OO 2.44E+06 6 Fe-59 5.02E+06 1.17E+07 4.52E+06 O.OOE+OO O.OOE+OO 3.69E+06 2.77E+07 7

Co-57 O.OOE+OO 1.92E+05 3.21E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.57E+06 8 Co-58 O.OOE+OO 7.40E+05

1. 71E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+07 9 Co-60 O.OOE+OO 2.27E+06 5.11E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.96E+07 10 Zn-65

1. 81E+08 6.27E+08 2.93E+08 O.OOE+OO 4.01E+08 O.OOE+OO 2.66E+08 11 Se-75 O.OOE+OO 2.49E+08 9.78E+07 O.OOE+OO 3.66E+08 O.OOE+OO 2.54E+07 12 Rb-86 O.OOE+OO 4.79E+08 2.25E+08 O.OOE+OO O.OOE+OO O.OOE+OO 7.09E+07 13 Sr-89 2.56E+08 O.OOE+OO 7.34E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.05E+07 14 Sr-90 5.36E+09 O.OOE+OO 1.32E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+08 15 Y-91 1.50E+03 O.OOE+OO 4.0lE+Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.14E+05 16 Zr-95 1.55E+02 4.90E+Ol 3.37E+Ol O.OOE+OO 7.19E+Ol O.OOE+OO 1.13E+05 17 Nb-95 1.39E+04 7.69E+03 4.23E+03 O.OOE+OO 7.45E+03 O.OOE+OO 3.29E+07 18 Nb-97 6.15E-13 1.53E-13 5.57E-14 O.OOE+OO 1.79E-13 O.OOE+OO 3.65E-09 19 Mo-99 O.OOE+OO 4.56E+06 8.70E+05 O.OOE+OO 1.04E+07 O.OOE+OO 8.17E+06 20 Tc-99rn 5.88E-01 1.64E+OO 2.13E+Ol O.OOE+OO 2.45E+Ol

9. llE-01 1.08E+03 21 Ru-103 1.77E+02 O.OOE+OO 7.56E+Ol O.OOE+OO 6.24E+02 O.OOE+OO 1.48E+04 22 Ru-106 2.44E+03 O.OOE+OO 3.98E+02 O.OOE+OO 6.10E+03 O.OOE+OO 1.52E+05 23 Ag-llOm 8.24E+06 7.80E+06 4.75E+06 O.OOE+OO

1. 49E+07 O.OOE+OO 2.19E+09 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m 7.61E+06 2.70E+06 9.05E+05

1. 81E+06 3.08E+07 O.OOE+OO 1.90E+07 28 Te-129m

1. 09E+07 4.03E+06

1. 72E+06 3.51E+06 4.55E+07 O.OOE+OO 4.08E+07 29 I-131 5.48E+07 7.67E+07 4.12E+07 2.24E+10 1.32E+08 O.OOE+OO 1.52E+07 30 I-133 7.21E+05 l.22E+06 3.73E+05

1. 71E+08 2.15E+06 O.OOE+OO 9.26E+05 31 Cs-134 8.llE+OB 1.91E+09 8.86E+08 O.OOE+OO 6.07E+08 2.32E+08 2.38E+07 32 Cs-136 4.56E+07 1.80E+08

1. 21E+08 O.OOE+OO 9.78E+07

1. 54E+07 1.45E+07 33 Cs-137 1.09E+09 l.44E+09 5.03E+08 O.OOE+OO 4.91E+08 1.91E+OB 2.06E+07 34 Ba-140 4.94E+06 6.06E+03 3.18E+05 O.OOE+OO 2.05E+03 4.07E+03 7.62E+06 35 La-140 8.27E-01 4.06E-01 1.0BE-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+04 36 Ce-141 B.79E+02 5.87E+02 6.74E+Ol O.OOE+OO 2.76E+02 0.00E+OO 1.68E+06 37 Cei-144 5.60E+04 2.32E+04 3.01E+03 O.OOE+OO 1.39E+04 O.OOE+OO 1.41E+07 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Proccdurc Number.

l/2-0DC-2.02

Title:

Unit Level OfUae:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revwon:

Page Number:

11 109 nfB1 ATTACHMENT J Page 18 of 19 P&I ORGAN DOSE FACTORS Table 2.3-19 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/vr per uCi/sec)

Pathway -

Goat Milk Age Group ~ Child Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1

H-3 O.OOE+OO

1. 88E+02 l.88E+02 1.88E+02

1. 88E+02

1. 88E+02 1.88E+02 2

C-14 l.98E+05 3.95E+04 3.95E+04 3.95E+04 3.95E+04 3.95E+04 3.95E+04 3

P-32 7.91E+09 3.70E+08 3.05E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.19E+08 4 Cr-51 O.OOE+OO O.OOE+OO 1.02E+04 5.64E+03 1.54E+03 1.03E+04 5.39E+05 5

Mn-54 O.OOE+OO 1.78E+06 4.74E+05 O.OOE+OO 4.99E+05 O.OOE+OO 1.49E+06 6 Fe-59 1.16E+07

1. 88E+07 9.38E+06 O.OOE+OO O.OOE+OO 5.46E+06 1.96E+07 7

Co-57 O.OOE+OO 3.27E+05 6.63E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+06 B Co-58 O.OOE+OO 1.13E+06 3.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 6.60E+06 9 Co-60 O.OOE+OO 3.53E+06 l.04E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E+07 10 Zn-65 3.54E+08 9.44E+08 5.87E+08 O.OOE+OO 5.95E+08 O.OOE+OO

1. 66E+08 11 Se-75 O.OOE+OO 4.66E+08 2.41E+OB O.OOE+OO 6.31E+08 O.OOE+OO 2.16E+07 12 Rb-86 O.OOE+OO 8.88E+08 5.46E+08 O.OOE+OO O.OOE+OO O.OOE+OO

5. 71E+07 13 Sr-89 6.35E+08 O.OOE+OO 1.81E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.46E+07 14 Sr-90 9.06E+09 O.OOE+OO 2.30E+09 O.OOE+OO O.OOE+OO O.OOE+OO

1. 22E+08 15 Y-91 3.70E+03 O.OOE+OO 9.89E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 4.93E+05 16 Zr-95 3.60E+02 7.92E+Ol 7.05E+Ol O.OOE+OO

1. 13E+02 O.OOE+OO 8.27E+o4 17 Nb-95 3.13E+04 1.22E+04

8. 71E+o3 O.OOE+OO 1.14E+04 O.OOE+OO 2.25E+07 18 Nb-97

1. 49E-12 2.70E-13 1.26E-13 O.OOE+OO 2.99E-13 O.OOE+OO 8.33E-08 19 Mo-99 O.OOE+OO 8.30E+06 2.05E+06 O.OOE+OO

1. 77E+07 O.OOE+OO 6.87E+06 20 Tc-99m 1.35E+OO 2.65E+OO 4.39E+Ol O.OOE+OO 3.84E+Ol

1. 34E+OO 1.51E+03 21 Ru-103 4.18E+02 O.OOE+OO 1.61E+02 O.OOE+OO 1.05E+03 O.OOE+OO 1.08E+04 22 Ru-106 7.79E+03 O.OOE+OO

9. 72E+02 O.OOE+OO 1.05E+04 O.OOE+OO

1. 21E+05 23 Ag-llOm 1.79E+07

1. 21E+07 9.65E+06 O.OOE+OO 2.25E+07 O.OOE+OO 1.44E+09 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m 1.88E+07 5.05E+06 2.23E+06 4.48E+06 5.35E+07 O.OOE+OO

1. 52E+07 28 Te-129m 2.68E+07 7.48E+06 4.16E+06 8.64E+06 7.87E+07 O.OOE+OO 3.27E+07 29 I-131 1.33E+08 1.34E+08 7.60E+07 4.42E+10 2.19E+08 O.OOE+OO 1.19E+07 30 I-133

1. 75E+06 2.17E+06 8.20E+05 4.03E+08 3.61E+06 O.OOE+OO 8.73E+05 31 Cs-134

1. 87E+09 3.07E+09 6.48E+08 O.OOE+OO 9.52E+08 3.42E+08 1.66E+07 32 C:,-136 1.03E+08 2.83E+08

1. 83E+08 O.OOE+OO 1.51E+08 2.25E+07 9.95E+06 33 Cs-137 2.62E+09 2.50E+09 3.69E+08 O.OOE+OO B.16E+08 2.94E+08 1.57E+07 34 Ba-140 1.19E+07 1.05E+06 6.96E+05 O.OOE+OO 3.40E+03 6.23E+03 6.04E+06 35 La-140

1. 98E+OO 6.92E-01 2.33E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.93E+04 36 Ce-141 2.16E+03 1.08E+03 1.60E+03 O.OOE+OO 4.73E+02 O.OOE+OO 1.35E+06 37 Ce-144 1.38E+05 4.33E+04 7.37E+03 O.OOE+OO 2.40E+04 O.OOE+OO

1. 13E+07 All nuclides (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-001

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02

Title:

Unit:

Lewi OfUse:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 110 nf 131 ATI'ACHMENT J Page 19 of 19 P&I ORGAN DOSE FACTORS Table 2.3-20 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway -

Goat Milk Age Group -

Infant Nuclide Bone Liver T. Body Thyroid Kidney Lung G:r-LLI 1

H-3 O.OOE+OO

2. 86E+02 2.86E+02 2.86E+02

2. 86E+02 2.86E+02 2.86E+02 2

C-14 3.87E+05 8.27E+04 B.27E+04 B.27E+04 B.27E+04 8.27E+04 8.27E+04 3

P-32 l.63E+l0 9.59E+08 6.32E+OB 0.00E+OO O.OOE+OO O.OOE+OO 2.21E+08 4 Cr-51 O.OOE+OO O.OOE+OO l.61E+04 l.05E+04 2.29E+03 2.04E+04 4.69E+05 5 Mn-54 O.OOE+OO 3.31E+06 7.50E+05 O.OOE+OO 7.33E+05 O.OOE+OO l.21E+06 6 Fe-59 2.17E+07

3. 79E+07 l.50E+07 O.OOE+OO O.OOE+OO l.12E+07 l.81E+07 7 Co-57 O.OOE+OO 7.64E+05 l.24E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.60E+06 B Co-58 O.OOE+OO 2.26E+06 5.64E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.64E+06 9 Co-60 O.OOE+OO 7.20E+06 l.70E+07 O.OOE+OO 0.00E+OO O.OOE+OO

1. 71E+07 10 Zn-65 4.76E+08 l.63E+09 7.53E+08 O.OOE+OO 7.92E+08 O.OOE+OO l.3BE+09 11 Se-75 O.OOE+OO l.15E+09 4.96E+08 O.OOE+OO l.12E+09 O.OOE+OO 2.15E+07 12 Rb-86 O.OOE+OO 2.25E+09

1. 11E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.77E+07 13 Sr-89 l.21E+09 O.OOE+OO 3.46E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+07 14 Sr-90 9.86E+09 O.OOE+OO 2.51E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.23E+08 15 Y-91 6.94E+03 O.OOE+OO l.85E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.98E+05 16 Zr-95 6.40E+02 l.56E+02 l.11E+02 O.OOE+OO l.68E+02 O.OOE+OO 7.77E+04 17 Nb-95 5.84E+04 2.41E+04 l.39E+04 O.OOE+OO

1. 72E+04 O.OOE+OO 2.03E+07 18 Nb-97 3.lGE-12 6.74E-13 2.43E-13 O.OOE+OO 5.27E-13 O.OOE+OO 2.13E-07 19 Mo-99 O.OOE+OO 2.12E+07 4.14E+06 O.OOE+OO 3.17E+07 O.OOE+OO 6.99E+06 20 Tc-99m 2.81E+OO 5.79E+OO 7.46E+Ol O.OOE+OO 6.23E+Ol 3.03E+OO l.6BE+03 21 Ru-103 8.47E+02 0.00E+OO 2.83E+02 O.OOE+OO l.76E+03 O.OOE+OO l.03E+04 22 Ru-106

1. 60E+04 O.OOE+OO 2.00E+03 O.OOE+OO l.90E+04 O.OOE+OO l.22E+05 23 Ag-llOm 3.30E+07 2.41E+07 l.60E+07 O.OOE+OO 3.45E+07 O.OOE+OO l.25E+09 24 Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO 26 Sb-126 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 Te-127m 3.80E+07 l.26E+07 4.59E+06

1. 10E+07 9.35E+07 O.OOE+OO 1.53E+07 28 Te-129m 5.50E+07

1. 89E+07 8.47E+06 2.11E+07 1.38E+08 O.OOE+OO 3.28E+07 29 I-131

2. 77E+08 3.27E+OB

1. 44E+08

1. 07E+ll 3.82E+08 O.OOE+OO l.17E+07 30 I-133 3.70E+06 5.39E+06

1. 58E+06 9.80E+08 6.34E+06 O.OOE+OO 9.12E+05 31 Cs-134 3.02E+09 5.62E+09 5.68E+08 O.OOE+OO l.45E+09 5.93E+08 l.53E+07 32 Cs-136 2.0lE+OB 5.92E+08 2.21E+08 O.OOE+OO 2.36E+08 4.82E+07 8.99E+06 33 Cs-137 4.17E+09 4.89E+09 3.46E+OB O.OOE+OO l.31E+09 5.31E+08 l.53E+07 34 Ba-140 2.45E+07 2.45E+04 l.26E+06 O.OOE+OO 5.83E+03 l.51E+04 6.03E+06 35 La-140 4.14E+OO l.63E+OO 4.19E-01 O.OOE+OO O.OOE+OO O.OOE+OO l.92E+04 36 Ce-141 4.29E+03 2.62E+03 3.08E+02 O.OOE+OO 8.07E+02 O.OOE+OO

1. 35E+06 37 Ce-144 l.98E+05 B.11E+04 l.11E+04 O.OOE+OO 3.2BE+04 O.OOE+OO 1.14E+07 All nuclide.s (except H-3 and C-14) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28 C-14 calculated per ERS-LMR-001

SECTOR N

NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW TABLE2.3-21 PV-1/2 DEPOSffiON PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR (meters~

DISTANCES TO THE CONTROL LOCATIONS, IN Mll,ES 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 6.00E-10 8.60E-09 3.14E-09 l.76E-09 8.12E-10 5.70E-10 424E-10 329E-10 6.66E-10 5.64E-09 l.98E-09 2.55E-09 1.33E-09 1.07E-09 6.75E-10 5.23E-10 1.03E-09 l.57E-09 l.32E-09 3.62E-09 2.63E-09 1.64E-09 1.23E-09 6.13E-10 l.13E-09 l.55E-09 3.69E-09 327E-09 2.3IE-09 129E-09 121E-09 6.78E-10 l.35E-09 1.28E-08 4.09E-09 3.12E-09 1.91E-09 1.36E-09 1.0lE-09 7.83E-10 9.82E-10 7.85E-09 4.40E-09 2.46E-09 1.47E-09 1.03E-09 5.65E-10 5.0SE-10 2.76E-09 6.41E-09 3.52E-09 l.97E-09 l.18E-09 827E-10 5.68E-10 4.40E-10 222E-09 4.66E-09 3.0lE-09 l.68E-09 1.02E-09 7.14E-10 4.25E-10 3.29E-10 3.00E-09 4.81E-09 3.76E-09 2.l0E-09 1.36E-09 9.52E-10 5.12E-10 3.96E-10 l.44E-08 2.89E-09 7.83E-10 8.84E-10 5.70E-10 4.00E-10 2.55E-10 l.98E-10 l.89E-08 5.55E-09 l.55E-09 8.71E-10 2.61E-10 3.94E-10 l.57E-10 2.50E-10 l.57E-09 6.63E-09 l.36E-09 1.04E-09 5.44E-10 2.39E-10 3.84E-10 2.98E-10 3.78E-10 2.95E-09 1.84E-09 l.03E-09 6.63E-10 4.66E-10 1.37E-10 2.68E-10 4.54E-10 4.13E-10 3.09E-10 4.71E-10 7.35E-10 5.16E-10 1.93E-10 l.I0E-10 4.52E-10 4.09E-10 2.86E-10 l.18E-09 7.04E-10 4.94E-10 3.37E-10 2.lOE-10 3.40E-10 2.05E-09 1.63E-09 9.12E-10 5.86E-10 4.13E-10 2.79E-10 2.16E-10 4.0 - 4.5 4.5 - 5.0 2.63E-10 2.15E-10 4.56E-10 3.74E-10 7.85E-10 6.42E-10 6.72E-10 3.89E-10 4.15E-10 5.IOE-10 3.25E-10 3.00E-10 2.93E-10 2.43E-10 2.19E-10 1.80E-10 2.68E-10 2.20E-10 1.84E-10 1.SlE-10 2.54E-10 2.08E-10 2.17E-10 1.78E-10 l.12E-10 1.75E-10 l.12E-10 1.80E-10 2.09E-10 1.71E-10 1.73E-10 l.42E-10 8

I V,

~

Cl.l g

("')

~

Cl.l § Cl.l

0 g

t:,

TABLE 2.3-22

(")

~

CV-I AND CV-2 DEPOSffiON PARAMETERS (D/Q) FOR

~

CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters~

CZl to

(")

l:I:l 0

(0 I

c::::

~

CZl l:I:l (0

DISTANCES TO TIIE CONTROL LOCATIONS, IN MILES 1-rj

~

i 0

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::::

~ -

CZl N

4.46E-08 7.73E-09 3.24E-09 l.81E-09 l.08E-09 7.57E-10 5.16E-I0 4.00E-10 2.91E-10 2.38E-10

~

(0

~

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

~

0 NE 7.32E-08 l.27E-08 6.21E-09 3.47E-09 2.24E-09 l.57E-09 l.00E-09 7.77E-10 5.69E-10 4.66E-10 CZl

~

ENE 7.77E-08 l.35E-08 6.51E-09 3.64E-09 2.50E-09 l.76E-09 l.31E-09 l.0lE--09 6.58E-10 5.39E-10 l:I:l (0

ij ~ ~

~

en 0 ~ (")

s-E 6.0SE-08 l.05E--08 3.79E-09 2.12E-09 l.37E-09 9.59E-10 6.54E-10 5.06E-10 4.0SE-10 3.32E-10 s ;'. I

~-

0 ESE 3.23E--08 5.60E-09 2.54E-09 l.42E-09 8.46E-10 5.94E-10 4.0SE-10 3.14E-10 2.28E-10 l.87E-10 oa.

t:S Z---l SE 3.29E-08 5.70E-09 2.59E-09 l.45E-09 9.32E-I0 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 I ~

SSE 2.84E-08 4.92E-09 2.06E-09 l.ISE-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 l.85E-10 l.52E-10 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-10 l.96E-10 !

,,;i

§'. I SSW 2.61E-08 4.52E-09 l.60E--09 8.97E-10 5.78E-10 4.06E-10 3.02E-I0 2.34E-10 l.70E-I0 l.39E ~I..... I"?"

0

..... ~ N SW 3.06E-08 5.30E-09 2.62E-09 l.47E-09 8.0lE-10 5.62E-10 4.18E-10 3.24E-10 2.35E-10 l.93E-10 I Vi WSW 4.60E-08 7.97E-09 3.34E-09 l.87E-09 l.20E-09 8.45E-10 5.87E-I0 4.55E-10 3.38E-10 2.77E-10

~

sf i ii 6*

CZl z

t:,

[Q 6.49E-08 l.13E--08 4.72E--09 2.64E-09 l.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.ISE-10

~,

(")

w

~ ~ v.dr ~

WNW 9.25E-08 l.60E--08 6.43E-09 3.60E-09 2.21E-09 l.55E--09 l.16E-09 8.96E-10 5.79E-10 4.75E-10

~-- ~

~

NW l.19E--07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.I0E-09 l.56E-09 l.21E-09 7.83E-I0 6.4IE-10

~

CD I NNW 5.22E--08 9.04E-09 3.79E-09 2.12E-09 l.28E-09 9.00E-10 6.25E-I0 4.84E-10 3.59E-10 2.94E-10

Beaver Valley Power Station Trtlc:

Procedure, Number:

l/2-ODC-2.02 Unit Level OfUac:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS RoviJion; Page Number.

11 1 B nfBl ATTACIIMENT K Page 3 of7 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (0-5 MILES)

TABLE 2.3-23 VV-1 AND VV-2 DEPOSITTON PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR (meters-2)

Same as Table 2.3-22

(

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02 Trtle:

Unit LevolOfUso:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Rcvisioo:

Page Number:

11 114 of 131 ATTACHMENT K Page 4 of7 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (0-5 :MILES)

TABLE 2.3-24 TV-2 DEPOSIDON PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HR.SNR OR> 150 HR.S/QTR (meters*2)

Same as Table 2.3-22 I

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.02

Title:

Unit:

Level OfUsc:

1 /?.

General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number.

11 114:i nf 111 ATTACHMENT K Page 5 of7 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (0-5 MILES)

TABLE 2.3-25 CB-2 DEPOSffiON PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR (meters-2)

Same as Table 2.3-22

Beaver Valley Power Station

Title:

Procedure Number:

l/2-0DC-2.02 Unit:

Level OfU5e:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS R.emion:

Page Number.

11 116 of 131 ATTACHMENT K Page 6 of7 CONTINUOUS RELEASE DEPOSIDON PARAMETERS (0-5 MILES)

TABLE 2.3-26 DV-2 DEPOSIDON 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-ODC-2.02

Title:

Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revmon:

Page Number:

11 117 nf 111 ATTACHMENT K Page 7 of7 CONTINUOUS RELEASE DEPOSIDON PARAMETERS (0-5 MILES)

TABLE 2.3-27 WV-2 DEPOSIDON PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR> 150 HRS/QTR (meters*2)

Same as Table 2.3-22 I

I

Beaver Valley Power Station

Title:

Procedure Number:

l/2-ODC-2.02 Unit Level Of Use:

l /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Reviaion:

Page Number.

11 11 R of 111 ATTACHMENT L Page 1 of7 CONTINUOUS RELEASE DEPOSIDON 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)

INDNIDUAL 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 11.000 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 1.710 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

Title:

Proccdme Number:

l/2-0DC-2.02 Unit Level OfUse:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 119 of 13]

ATTACHMENT L Page2 of7 CONTINUOUS RELEASE DEPOSITTON 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 5.59 126

.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 39.10 223 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

Title:

Procedure Number:

l/2-0DC-2.02 Unit:

Lewi OfUac:

] /2 General Skill Reference ODCM: GASEOUS EFFLUENTS ATTACHMENT L Page 3 of7 Revision:

Page Number.

11 1?0nf131 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-30 W-1 AND W-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

Title:

Procedure Number:

l/2-0DC-2.02 Unit:

Lewi OfUse:

1/2 General Skill Reference ODCM: GASEOUS E~UENTS Revision:

Page Number:

11 121 of 131 ATTACHMENT L Page4 of7 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-31 TV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRSNR OR> 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED 1N 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

20.20 2.05

.693

.847 2.190 NNE 34.90 2.02

.459 1.850 2.110 NE 54.20 29.30

.455

.078

.455 30.400 ENE 57.50 8.92

.661 32.200 E

38.10 3.90

.382 1.020 1.020 22.700 ESE 18.60 3.56 1.380 3.560 3.560 SE 19.00 3.03

.351

.351 1.100 3.030 SSE 13.30 2.65

.318

.094 2.570 3.690 s

11.30 10.40

.934 1.860 1.950 SSW 6.44 1.26

.664

.266 1.260 4.430 SW 3.95 2.21 1.320 1.920 2.210 WSW 25.10 2.65

.597 2.380 2.650 w

28.40 1.23

.646

.961 1.230 WNW 30.90 2.23 1.490

.045 2.230 2.230 NW 56.10 14.90

.276 1.980 15.500 NNW 25.10 6.53

.068 1.100 9.920

Beaver Valley Power Station Trtle:

Procedure Number.

l/2-0DC-2.02 Unit Level OfUse:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number.

11 1??.nf131 ATTACHMENT L Page 5 of7 CONTINUOUS RELEASE DEPOSITTON P.ARMvIBTERS (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)

(lE-9 meters-2)

Same as Table 2.3-31

Beaver Valley Power Station Trtle:

Procedure Number:

l/2-0DC-2.02 Unit Level OfUsc:

1 /?.

General Skill Reference ODCM: GASEOUS EFFLUENTS R.eviJ:loo:

Page Nomb<<:

11 1?~nfl31 ATTACHMENT L Page 6 of7 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-33 DV-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

Title:

Proccdmc Nmnbcr.

l/2-0DC-2.02 Unit Level Of Use:

1/2 General Skill Reference ODCM: GASEOUS EFFLUENTS ATTACHMENT L Page 7 of7 Revision:

Page Number:

] ]

1 ?A. of 131 CONTINUOUS RELEASE DEPOSITTON PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-34 WV-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)

Same u Table 2.3-29

Beaver Valley Power Station

Title:

Procedure Number:

l/2-0DC-2.02 Unit 1/2 Level OfUae:

General Skill Reference ODCM: GASEOUS EFFLUENTS Reviaion:

Page Number:

11 1?.c; nfB1 ATTACHMENT M Page 1 of3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-35 CV-I AND CV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES s500 HRSNR OR S150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIBD IN ATTACHMENT E TABLE 2.2-3)

(sec/m3)

INDNIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK l\\.fEAT 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 I

NE 4.59E-5 2.21E-5 6.05E-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 5.15E-7 1.17E-6 l.17E-6 1.78E-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 1.llE-6 3.92E-7 6.BE-6 8.49E-6 s

2.15E-5 3.03E-6 2.76E-6 4.93E-6 5.14E-6 SSW 2.18E-5 6.58E-6 3.81E-6 1.82E-6 6.58E-6 1.78E-5 SW 1.82E-5 1.03E-5 6.67E-6 9.12E-6 1.03E-5 WSW l.09E-4 1.29E-5 4.lOE-6 1.19E-5 l.29E-5 w

1.49E-4 1.05E-5 6.55E-6 8.77E-6 l.0SE-5 WNW 1.91E-4 1.72E-5 1.28E-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 1.35E-6 9.27E-6 529E-5

Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980

Beaver Valley Power Station T"rtlo:

Proccduro Number.

l/2-ODC-2.02 Unit Level Of Use:

1 /2 General Skill Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

11 1 ?.6 of 131 ATTACHMENT M Page2 of3 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 S150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(sec/m3)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MJLK MILK MEAT SECTOR*

BOUNDARY GARDEN cow GOAT ANIMAL RESIDENCE N

9.75E-5 l.OOE-5 4.21E-6 4.95E-6 l.06E-5 NNE 3.78E-5 5.llE-6 l.43E-6 4.72E-6 5.30E-6 NE 6.13E-5 2.70E-5 6.20E-7 l.40E-7 620E-7 2.81E-5 ENE 4.83E-5 5.58E-6 5.71E-7 2.24E-5 E

3.66E-5 3.99E-6 5.25E-7 l.19E-6 1.19E-6 2.I0E-5 ESE 2.99E-5 6.13E-6 2.43E-6 6.13E-6 6.13E-6 SE 2.55E-5 5.29E-6 8.24E-7 8.24E-7 2.13E-6 5.29E-6 SSE 2.65E-5 6.72E-6 1.12E-6 3.95E-7 6.53E-6 9.22E-6 s

2.52E-5 3.14E-6 2.83E-6 5.29E-6 5.53E-6 SSW 2.60E-5 7.34E-6 4.15E-6 l.92E-6 7.34E-6 2.09E-5 SW 2.13E-5 1.18E-5 7.41E-6 1.04E-5 1.18E-5 WSW l.34E-4 1.51E-5 4.46E-6 1.38E-5 l.51E-5 w

l.77E-4 l.25E-5 7.40E-6 1.02E-5 l.25E-5 WNW 2.33E-4 2.07E-5 l.49E-5 l.30E-6 2.07E-5 2.07E-5 NW 3.32E-4 8.57E-5 4.24E-6 l.64E-5 8.85E-5 NNW l.90E-4 4.69E-5 l.45E-6 1.09E-5 6.75E-5

Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980

Beaver Valley Power Station

Title:

Procedure Number:

l/2-0DC-2.02 Unit:

Level Of Use:

l /2 General Skill Reference ODCM: GASEOUS EFFLUENTS R.cviaion:

Pago Number.

11 l?,7 of n1 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)

(sedm3)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*

BOUNDARY GARDEN cow GOAT ANIMAL RESIDENCE N

3.09E-9 3.30E-6 1.13E-6 l.34E-6 3.36E-6 NNE 2.85E-9 2.68E-6 6.52E-7 2.47E-6 2.68E-6 NE 2.02E-10 7.42E-9 5.44E-7 l.24E-7 5.44E-7 5.51E-9 ENE 1.02E-9 3.21E-6 6.29E-7 l.67E-9 E

2.15E-9 2.91E-6 4.96E-7 1.14E-6 1.14E-6 2.91E-6 ESE 6.90E-9 4.97E-6 1.95E-6 4.97E-6 4.81E-6 SE 2.91E-6 3.52E-6 6.02E-7 6.02E-7 1.43E-6 3.52E-6 SSE 4.91E-6 3.56E-6 6.53E-7 2.18E-7 3.47E-6 4.71E-6 s

2.41E-6 l.78E-6 1.65E-6 2.84E-6 2.96E-6 SSW 4.83E-6 2.52E-6 1.S0E-6 6.60E-7 2.52E-6 3.96E-6 SW 4.82E-6 2.75E-6 l.78E-6 2.44E-6 2.75E-6 WSW 5.77E-7 2.81E-6 8.79E-7 2.57E-6 2.81E-6 w

2.88E-9 1.68E-6 4.89E-7 1.37E-6 1.68E-6 WNW 3.40E-9 1.61E-6 1.13E-6 l.lOE-7 1.61E-6 l.61E-6 NW l.34E-9 3.31E-8 2.03E-7 1.07E-6 3.lOE-8 NNW 1.52E-9 3.73E-6 l.73E-7 1.31E-6 3.81E-6

Measured relevant to BV-1 natural draft cooling tower Period of Record: 1976 - 1980

TABLE 2.3-38 PV-1/2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES ~00 HRS/YR OR ~150 HRS/QTR (sec/m3)

DISTANCES TO TIIB CONTROL LOCATIONS, IN MILES 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 N

2.75E-15 1.07E-5 4.lOE-6 2.61E-6 1.51E-6 1.13E-6 8.84E-7 7.13E-7 NNE 5.90E-17 5.39E-6 2.83E-6 2.19E-6 1.36E-6 1.13E-6 8.05E-7 6.51E-7 NE 4.45E-16 1.67E-8 7.39E-8 2.28E-6 1.72E-6 l.19E-6 928E-7 6.76E-7 ENE l.92E-15 8.87E-8 2.60E-6 22IE-6 l.66E-6 1.13E-6 925E-7 7.23E-7 E

l.84E-15 5.lOE-6 2.77E-6 2.23E-6 l.44E-6 1.12E-6 8.74E-7 6.92E-7 ESE 2.96E-13 526E-6 3.48E-6 2.04E-6 l.34E-6 9.93E-7 6.70E-7 5.76E-7 SE 9.16E-8 3.13E-6 3.38E-6 1.99E-6 l.3IE-6 9.58E-7 7.14E-7 5.74E-7 SSE 3.50E-8 4.86E-6 3.33E-6 l.95E-6 1.29E-6 9.42E-7 6.55E-7 524E-7 s

l.22E-7 4.12E-6 3.97E-6 2.34E-6 I.59E-6 l.17E-6 7.75E-7 6.24E-7 SSW I.75E-5 6.22E-6 2.84E-6 2.18E-6 I.48E-6 l.08E-6 7.83E-7 6.31E-7 SW 2.08E-5 9.1 lE-6 3.47E-6 2.19E-6 l.25E-6 1.llE-6 8.19E-7 7.17E-7 WSW 8.56E-8 9.35E-6 3.16E-6 2.29E-6 l.46E-6 l.0lE-6 9.06E-7 7.52E-7 w

5.44E-17 4.52E-6 42IE-6 2.49E-6 l.69E-6 1.25E-6 4.86E-7 7.68E-7 WNW 9.25E-18 1.44E-8 5.66E-8 l.92E-6 l.59E-6 l.17E-6 7.75E-7 4.61E-7 NW 2.61E-16 1.98E-8 8.37E-8 224E-6 1.46E-6 1.08E-6 8.09E-7 6.12E-7 NNW l.91E-15 3.91E-6 3.66E-6 2.15E-6 l.40E-6 1.08E-6 8.03E-7 6.48E-7 0

t:1 2

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'""1 I n

i:::

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en en 4.0 - 4.5 4.5 - 5.0 tr.1 t:1 r;l 5.93E-7 5.06E-7

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5.64E-7 4.81E-7

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7.34E-7 5.32E-7 0~ I 6.06E-7 3.82E-7 z-f \\

5.llE-7 4.82E-7 4.37E-7 3.83E-7 4.32E-7 3.68E-7 3.95E-7 3.32E-7

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4.74E-7 4.00E-7

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5.62E-7 4.77E-7 0

...... r I

6.89E-7 5.85E-7 Vi 5.99E-7 5.07E-7

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5.80E-7 5.48E-7 en l

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Beaver Valley Power Station

Title:

ODCM: GASEOUS EFFLUENTS n111Ltlll Clll.lm ATTACHMENT 0 Page 1 of 1 GASEOUS RADW ASTE SYSTEM FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM IIIUt 1 CWIDIOI I.., na I 1-,y flllt I nmrna DIIIIIJnD IIIOT Z..

COIIIIIIOII IJIQ! TN I

,Na, IMI I 111a, rMI I jmmtrwl lrmt TN I IIIIIP..

1111.111* All OIC!IDIIIIU.IIII Procedure Numbl:r.

l/2-0DC-2.02 Unit Level OfUse:

General Skill Reference Reviaion:

Page Number:

Beaver Valley Power Station

Title:

Procedum Number:

l/2-0DC-2.02 Unit Level OfU1e:

*J General Skill Reference ODCM: GASEOUSEFFLUENTS AITACHMENTP Page 1 of 1

'Revism:

BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS PIGURI 2..4-1

&V-1 AND 2 GASIOUS IFFI.UBIIT UWS£ POlltt'S 0

CJ 1, U.lt h

\\ltnlflttkll'I -.

D ll-..tfan I. Lftft 11 Clfflal~ f IL.CU Vent:

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U0 lltter&

4. Uirit 2:

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Pagc,Number:

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.. 411t Shippingport 411t' -......,

Thi Site Boundary for

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Liquid Effluent does not include the areas over the 411t,.

Ohio River.

With thi11 exception I

the site Boundarie11 are identical.

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