Text

RTL A9.621B, Procedure 1/2-ODC-2.02, Rev. 3, ODCM: Gaseous Effluents
	ML13126A045
Person / Time
Site:	Beaver Valley
Issue date:	01/25/2011
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	L-13-129 1/2-ODC-2.02, Rev. 3, RTL A9.621B
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RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.02 ODCM: GASEOUS EFFLUENTS Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 3

Level Of Use In-Field Reference Safety Related Procedure Yes Effective Date 01/25/11

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1 2 of 133 TABLE OF CONTENTS 1.0 PURPO SE.........................................................................................................................................

4 2.0 SCOPE..............................................................................................................................................

4 3.0 REFEREN CES AN D COM M ITM EN TS....................................................................................

4 3.1 References..............................................................................................................................

4 3.2 Com m itm ents.........................................................................................................................

6 4.0 RECORD S AN D FORM S............................................................................................................

7 4.1 Records...................................................................................................................................

7 4.2 Form s......................................................................................................................................

7 5.0 PRECA U TION S AN D LIM ITA TION S......................................................................................

7 6.0 A CCEPTAN CE CRITERIA.......................................................................................................

8 7.0 PREREQU ISITES............................................................................................................................

9 8.0 PRO CEDU RE...................................................................................................................................

9 8.1 A larm Setpoints.............................................................................................................

9 8.1.1 BV -1 M onitor A larm Setpoint D eterm ination.................................................

9 8.1.2 BV -2 M onitor A larm Setpoint D eterm ination.................................................

19 8.1.3 BV -1/2 M onitor A larm Setpoint D eterm ination...........................................

29 82 Compliance Wfith 0 CFR 20 Dose Rate Limits (ODCM CONTROL 3.112.1)...................................

36 8.2.1 D ose Rate D ue To N oble Gases......................................................................

36 8.2.2 D ose Rate D ue To Radioiodines A nd Particulates..........................................

43 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)

(G aseous)..............................................................................................................................

47 8.3.1 D ose Due To N oble Gases.............................................................................

47 8.3.2 D ose D ue To Radioiodines A nd Particulates................................................

54 8.4 G aseous Radw aste System.............................................................................................

71 8.4.1 BV-I Gaseous Radw aste System Com ponents..............................................

71 8.4.2 BV -2 G aseous Radw aste System Com ponents..............................................

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3 of 133 TABLE OF CONTENTS ATTACHMENT A ATTACHMENT B ATTACHMENT C ATTACHMENT D ATTACHMENT E ATTACHMENT F ATTACHMENT G ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENT K ATTACHMENT L ATTACHMENT M ATTACHMENT N ATTACHMENT 0 ATTACHMENT P ATTACHMENT Q GASEOUS SOURCE TERM........................................................................

75 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES............ 77 MODES OF GASEOUS RELEASE................................................... 79 RADION UCLIDE M IX.................................................................................

80 DISTANCES TO RELEASE POINTS..........................................................

82 0-5 MILE DISPERSION PARAMETERS......................................................

83 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS...................

90 ORGAN DOSE PARAMETERS....................................................................

92 MODES OF GASEOUS RELEASE................................................................

93 P&I ORGAN DOSE FACTORS...................................................................

94 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)..... 113 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL D IST A N C E S)....................................................................................................

120 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL D IST A N C E S)....................................................................................................

127 BATCH RELEASE DISPERSION PARAMETERS (0 - 5 MILES)................ 130 GASEOUS RADWASTE SYSTEM.................................................................

131 BV-I AND BV-2 GASEOUS EFFLUENT RELEASE POINTS..................... 132 SITE BOUNDARY FOR GASEOUS EFFLUENTS........................................

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4of 133 1.0 PURPOSE 1.1 This procedure provides the calculational methodology to be used for determination of the following release parameters.

1.1.1 Gaseous effluent monitor alarm setpoints 1.1.2 Gaseous effluent dose rate calculations 1.1.3 Gaseous effluent dose calculations 1.2 This procedure also provides information related to the following:

1.2.1 Gaseous Radwaste Treatment System.

1.2.2 Site Boundary used for gaseous effluents.

1.3 Prior to issuance of this procedure, these items were located in Section 2 and Section 5 of the old ODCM.

2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 References for BV-1 Gaseous Effluent Monitor Setpoints 3.1.1.1 Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412; Table 2.1-3 3.1.1.2 Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-1 3.1.1.3 BVPS Specification No. BVS 414, Table V Nuclide Data,; Table 1 and Figure 1, Table 3, and Figure 2, May 30, 1974 3.1.1.4 Calculation Package No.ERS-SFL-85-031, Unit 1 Gaseous Effluent Monitor Efficiency Data 3.1.1.5 Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.1.6 Calculation Package No.ERS-ATL-87-026,BVPS-1 and BVPS-2 ODCM T Factor Justification

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5 f 133 3.1.1.7 Letter ND1SHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B 3.1.1.8 Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.2 References for BV-2 Gaseous Effluent Monitor Setpoints 3.12.1 Calculation Package No.ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies 3.1.2.2 Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.2.3 Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-2 3.1.2.4 Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification 3.1.2.5 Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.3 References Used for other portions of this procedure 3.1.3.1 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.1.3.3 NUREG-0324; XOQDOQ Program for the Meteorological Evaluation of Routine Releases at 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 Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix 1, April 1977 3.1.3.6 NUREG-0 172, Age - Specific Radiation Dose Commitment Factors for a one-year Chronic Intake 3.1.3.7 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.3.8 1/2-ADM-0100, Procedure Writers Guide 3.1.3.9 NOP-SS-3001, Procedure Review and Approval

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3 6 of 133 3.1.3.10 CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit I Containment Vacuum Pump Source-Term in ODCM procedure 1/2-ODC-2.02, Attachment A, Table 2.1-l a.

3.1.3.11 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.

CA-16, Revise procedure 1/2-ODC-2.02 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.

3.1.3.12 Unit I Technical Specification Amendment No. 275 (LAR 1 A-302) to License No.

DPR-66. This amendment to the Unit 1 license was approved by the NRC on July 19, 2006.

3.1.3.13 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.

3.1.3.14 Engineering Change Package No. ECP-04-0440, Extended Power Uprate.

3.1.3.15 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure 1/2-ODC-2.02 to update the alarm setpoints of gaseous effluent radiation monitor for incorporation of the Extended Power Uprate per Unit I TS Amendment No. 275.

3.1.3.16 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.

3.1.3.17 Federal Guidance Report No. 11: Limiting Values of Radionuclide Intake And Air Concentration and Dose Conversion Factors For Inhalation, Submersion, and Ingestion, September 1988.

3.1.3.18 Federal Guidance Report No. 12: External Exposure to Radionuclides in Air, Water, and Soil, September 1993.

3.1.3.19 L. R. McKay (Ed.), A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment (ORNL-4992), Oak Ridge National Laboratory, 1975.

3.1.3.20 CR 10-85877, Selenium-75 (Se-75) discharge via U1/U2 Process Vent. CA-02 revises ODCM procedure 1/2-ODC-2.02 to include dose factors for Se-75.

3.2 Commitments 3.2.1 None

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7 of 133 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 ODCM CONTROLS applicable to dose rate apply to the site. The site dose rate is due to the summation of releases from both units.

5.2 ODCM CONTROLS applicable to accumulated dose apply individually to each unit.

5.3 Releases at the Beaver Valley site may be ground level or elevated in nature.

5.3.1 All ground level releases are identified with a specific unit in the determination of site dose rate and dose attributed to that unit.

5.3.2 Elevated releases from both units are considered to originate from a shared radwaste system and are discharged from a common release point, the Process Vent, at the top of the BV-I cooling tower.

5.4 At BV-1 and BV-2, the dose from continuous and batch (Gas Waste Storage Tanks) releases via the shared radwaste system (Process Vent) are normally apportioned equally to the units.

Other continuous and batch releases via non-shared radwaste systems shall be attributed to a specific unit. The only exception is a containment purge via the Process Vent which shall be attributed to a specific unit.

5.5 There is a difference in setpoint terminology presentations of the radiation monitoring systems of BV-1 and BV-2.

5.5.1 Where HIGH and HIGH-HIGH terminology are used for the BV-1 Victoreen monitors, ALERT and HIGH terminology are used for the BV-I Eberline SPING monitors and the BV-2 monitors.

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3 of 133 5.5.2 Also, BV-2 setpoints are presented in uCi/cc rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to the BV-2 raw data (cpm). The user is cautioned that the uCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice, setpoints determined for a calculated mix are correct for that mix. 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.

5.5.3 All BV-1 and BV-2 effluent monitors specified herein have Upper Alarm Setpoints established at 60 percent of the site limit, and Lower Alarm Setpoints established at 30 percent of the site limit.

5.6 A release may be batch or continuous in nature. Batch refers to releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment purges and ventings of systems or components with infrequent use.

5.6.1 Batch releases may be due to operational variations which result in radioactive releases greater than 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 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months or less in a calendar year, but not more than 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months in any quarter.

5.6.2 The batch relative concentration value has been calculated in accordance with the guidelines provided in NUREG-0324(3' 33 ) for short-term release.

5.6.3 IF simultaneous batch and continuous release out of one vent occurs, THEN use the lowest setpoint obtained according to Sections 8.1.1.1 through 8.1.3.2.

5.7 This procedure also contains information that was previously contained in Section 5 of the previous BV-1 and BV-2 Offsite Dose Calculation Manual.

5.7.1 In regards to this, the site boundary for gaseous effluents was included in this procedure.

5.7.2 The Site Boundary for Gaseous Effluents is shown in ATTACHMENT P Figure 5-1.

6.0 ACCEPTANCE CRITERIA 6.1 All 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, and Appendix I to 10 CFR 50, and not adversely impact the accuracy of effluent dose or alarm setpoint calculation. (3.1.3.2) 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100( 3 1.3.8) and 1/2-ADM-1640. (3.1.3.7) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-300 1(31.3.9) and 1/2-ADM-1640. (3.1.3.7)

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3 9_of_133 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.

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 8 effluent stream monitors, of which 3 are located at BV-I (alternates exists for these monitors), and 5 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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3 1_10 of 133 Monitor Setpoint Specifications Based On Fraction Of Site Limit UNIT RELEASE POINT MONITOR NO.

FRACTION OF SITE LIMITING DOSE RATE Upper Alarm (VV-1) Unit 1, Auxiliary Building Vent Pri.: RM-1VS-101B or Alt.: RM-1VS-109 (5) 60% (HIGH-HIGH) 60% (HIGH)

(CV-1) Unit 1, RX Containment/SLCRS Vent Pri.: RM-1VS-107B or 60% (HIGH-HIGH)

Alt.: RM-1VS-1 10 (5) 60% (HIGH)

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

Alt.: RM-1GW-109 (5) 60% (HIGH)

(CV-2), Unit 2, SLCRS Filtered Pathway 2HVS-RQ109E 60% (HIGH)

(VV-2), Unit 2, SLCRS Unfiltered Pathway 2HVS-RQ1O1B 60% (HIGH)

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

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

(CB-2), Condensate Polishing Building Vent 2HVL-RQI 12B 60% (HIGH)

Lower Alarm 30% (HIGH) 30% (ALERT) 30% (HIGH) 30% (ALERT) 30% (HIGH) 30% (ALERT) 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 30% of the site dose rate limit when any monitor is indicating a Lower Alarm.

The site dose rate is 60% of the site dose rate limit when any two monitors are indicating Lower Alarms.

The site dose rate is 60% of the site dose rate limit when any monitor is indicating an Upper Alarm.

The site dose rate is 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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11 of 133 8.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For VV-1 and CV-1 Ground Releases The table below gives the calculated monitor count rate above background (CR), in ncpm, and provides the equivalent monitor indication associated with the most limiting site dose rate limit (i.e.; 500 mrem/yr Total Border 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:

BV-1 ALARM SETPOINTS FOR GROUND RELEASES cpm ABOVE BACKGROUND

" Continuous Release Via The BV-I Auxiliary Building Vent (VV-1)

" Batch Release Of Containment Purge Via The BV-1 Auxiliary Building Vent (VV-1)

Continuous Release Via The BV-1 Rx Containment/SLCRS Vent (CV-1)

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

(P) PRIMARY*

MONITOR (A) ALTERNATE MONITOR (P)RM-1VS-1I0B (A)RM-1VS-109(5)

(P)RM-1VS-IOB (A)RM-1VS-109(5)

(P)RM-1VS-107B (A)RM-IVS-I 10(5)

(P)RM-1 VS-i 07B (A)RM-1VS-I 10(5)

CR 3000 1470 1200 1430 6440 3380 60%

SITE LIMIT UPPER ALARM

_< 1800

< 879

<718

<860 30%

SITE LIMIT UPPER ALARM

< 900

<440

<359

<430

< 3870

1930

< 2030

<1010 12,700

<7630 6660

< 4000 3810 2000

IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized.

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 GAS I BB (similar to NUREG-0017),(3134) 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.

a Discharge flow rate of 62,000 cfin for a VV-1 Continuous Release.

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1_3 1_12_of 133

" Discharge flow rate of 92,000 cfm for a VV-I Batch Release of Containment Purge.

This is comprised of 30,000 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 of 7,500 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 of BV-I Containment Purge via VV-1.

Batch release of BV-1 Containment Purge via CV-2.

8.1.1.1.1 BV-1 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:

The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-la.

The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by:

ZA Si-j

[2.1(1)-1]

EA where:

Ai = The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1 -la.

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1_3 13 of 133 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 Qt =

[2.1(1)-2]

(X/Q) ZK, Si where:

(X/Q),,

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/mn3) from ATTACHMENT F Table 2.2-5.

=

1.03E-4 sec/mr3 for continuous releases.

(X/q)v, 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/mi3) from ATTACHMENT M Table 2.3-36.

=

3.32E-4 sec/mr3 for batch release of containment purge.

(X/Q)CV The highest calculated annual average relative concentration of effluents released via CV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/mi3) from ATTACHMENT F Table 2.2-4.

=

9.24E-5 sec/mr3 for continuous releases.

(X/q)cv The highest calculated short term relative concentration of effluents released via CV-1 for any area at or beyond the unrestricted area boundary for any sectors (sec/mr3) from ATTACHMENT M Table 2.3-35.

3.08E-4 sec/mr3 for batch release of containment purge.

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

Si

=

From equation [2.1(1)-1] above.

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1 3 14 of 133 8.1.1.1.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure)

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

Qt =

3000 (X/Q) Z(Li + 1.1Mj) S5 where:

Li=

The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

Mi

=

The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m 3) 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) 8.1.1.1.4 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:

Qi = Si Qt

[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.

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1_3 15_of_133 8.1.1.1.5 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:

2. 12E-3 Q, Ci =

[2.1(1)-5]

F where:

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/min x 3.53E-5 ft3/cc).

8.1.1.1.6 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide. CR was determined by:

CR =

Ci Ei

[2.1(1)-6)]

where:

Ei = The detection efficiency of the monitor for noble gas radionuclide '"T (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.

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

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

HHSP = 0.60 x CR

[2.1(1)-7]

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

HSP = 0.30 x CR

[2.1(1)-8]

NOTE:

The values 0.60 for the HHSP and 0.30 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units.

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1_3 1_16_of_133 8.1.1.2 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.

8.1.1.2.1 BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-1 and CV-I during purging is determined as follows:

0 The maximum acceptable gaseous discharge flow rate (f) from VV-I and CV-1 (cfm) during purging based upon the whole body exposure limit is calculated by:

1.06 S T f=(X/q)

Ki Ci[21)-7 where:

1.06

= 500 mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit 2.12E-3

= unit conversion factor

= (60 sec/min x 3.53E-5 ft3/cc)

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 valve 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).(3116)

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__3 17_of_133 (X/q)vv The highest calculated short term relative concentration of effluents released via VV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/M 3) from ATTACHMENT M Table 2.3-36.

= 3.32E-4 sec/mr3 (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/m 3) from ATTACHMENT M Table 2.3-37.

3.08E-4 sec/mr3 Ki

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide 'T' (mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

Ci

= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.

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

6.36 ST 6.6=

[2.1(1)-18]

(X/q)

(Li + 1. 1 M) Ci where:

6.36 = 3000mrem/yrx2.12E-3 3000 mrem/yr

= dose rate limit 2.12E-3

= unit conversion factor

= (60 sec/min x 3.53E-5 ft3/cc)

Li

= The skin dose factor due to beta emissions from noble gas radionuclide "i" (mremryear/uCi/m 3) from ATTACHMENT G Table 2.2-11.

Mi

=

The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

(X/q) = Same as above.

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_18_of 133

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.

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

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

fZ CEi HHSP -

F where:

[2.1(1)-19]

f

=

The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 8.1.1.2.1.

F'

=

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

=

92,000 cfm for VV-1

=

56,800 cfm for CV-1 Ci

= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.

Ei

=

The detection efficiency of the monitor for noble gas radionuclide "i" (cpmluCi/cc) from ATTACHMENT B Table 2.1-2a.

When a 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]

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3 19 of 133 8.1.2 BV-2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determinations.

8.1.2.1 BV-2 Setpoint Determination Based On A Calculated Mix For VV-2, CV-2, DV-2. WV-2 and CB-2 Ground Releases.

The table below gives the calculated monitor count rate above background (CR) in ncpm, and provides the equivalent monitor indication (DV) in net uCi/cc associated with the most limiting site dose rate limit (i.e., 500 mrem/yr Total Body or 3000 mrem/yr Skin). The HIGH alarm setpoint (HSP) in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCi/cc above background for each vent and operational condition shall be as follows:

BV2 ALARM SETPOINTS FOR GROUND RELEASES uCi/cc ABOVE BACKGROUND (unless otherwise specified) 60%

SITE S

LIMIT UPPER DV ALARM 30%

ITE LIMI1 LOWER ALARM CR MONITOR ncpm

Continuous Release Via The BV-2 SLCRS Unfiltered Pathway (VV-2)

" Batch Release Of Containment Purge Via The BV-2 SLCRS Unfiltered Pathway (VV-2)

" Continuous Release Via The BV-2 SLCRS Filtered Pathway (CV-2)

" Batch Release Of Containment Purge Via The BV-2 SLCRS Filtered Pathway (CV-2)

" Continuous Release Via The BV-2 Condensate Polishing Building Vent (CB-2)

" Continuous Release Via The BV-2 Decontamination Building Vent (DV-2)

" Continuous Release Via The BV-2 Waste Gas Storage Vault Vent (WV-2) 2HVS-RQ101B 2HVS-RQ101B 2HVS-RQ 1 09E 2HVS-RQ109E 2HVL-RQ 1l2B 2RMQ-RQ301B 2RMQ-RQ303B 8260 3.01E-4 < 1.81E-4 < 9.04E-5 2020 7.39E-5 < 4.43E-5 < 2.22E-5 4320 2940

_ 1770

883 pCi/sec

[tCi/sec jiCi/sec 16,400 1130 gCi/sec 676

338

ýICi/sec

ýLCi/sec 28.,900 1.61E-3 *<9.63E-4 <4.82E-4 56,600 3.15E-3

_< 1.89E-3 < 9.44E-4 912,000 2.58E-2 _< 1.55E-2 < 7.74E-3

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320 of 133 The setpoints were determined using the following conditions and information:

Source terms given in ATTACHMENT A Table 2.1-l b. These gaseous source terms were derived from Stone & Webster computer code GAS 1BB (similar to NUREG-0017)(3 134) and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-l b does not include particulates and iodines, which are not used in site noble gas dose rate calculations.

The Containment Building Purge radionuclide mix was utilized for the purposes of determining an alarm setpoint for the SLCRS Unfiltered Pathway on the basis of the proximity of the contiguous areas.

The Decontamination Building and Condensate Polishing Building ventilation exhaust are 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.

e. 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 2.1-1 b under Gaseous Waste System.

Onsite meteorological data for the period January 1, 1976 through December 31, 1980.

Discharge flow rate of 23,700 cfm for a VV-2 Continuous Release.

Discharge flow rate of 53,700 cfm for a VV-2 Batch Release of Containment Purge. This is comprised of 30,000 cfm from the containment purge plus 23,700 cfm from the CV-2.

Discharge flow rate of 59,000 cfm for a CV-2 Continuous Release.

Discharge flow rate of 59,000 cfm for a CV-2 Batch Release of Containment Purge. This is comprised of 7,500 cfm from the containment purge plus 51,500 cfm from CV-2.

Discharge flow rate of 30,556 cfm for a CB-2 Continuous Release.

Discharge flow rate of 12,400 cfm for DV-2 Continuous Release.

a Discharge flow rate of 2,000 cfm for WV-2 Continuous Release.

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1_3 1

21 of_133 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 of BV-2 Containment Purge via VV-2..

Batch release of BV-2 Containment Purge via CV-2.

Continuous release via CB-2.

Continuous release via DV-2.

" Continuous release via WV-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 2.1-1 b.

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:

8.1.2.1.1 Si = Ai Ai

[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-l b. However, SINCE releases via CB-2 and DV-2 do not have a valid source term mix, THEN the noble gas radioactivity concentration is assumed to be Xe-133.

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3 1_22 of 133 8.1.2.1.2 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 (X/Q)

K, Sj

[2.1(2)-2]

where:

(X/Q)v

=

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/mr

) from ATTACHMENT F Table 2.2-5.

=

1.03E-4 sec/mr3 for continuous releases.

(X/q)vv

=

The short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT M Table 2.3-36.

= 3.32E-4 sec/m 3 for batch release of containment purge.

(X/Q).,

=

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/mr3) from ATTACHMENT F Table 2.2-4.

=

9.24E-5 sec/m 3 for continuous releases.

= 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/mr3) from ATTACHMENT M Table 2.3-35.

= 3.08E-4 sec/mr3 for batch release of containment purge.

(X/Q)CP

=

The highest calculated annual average relative concentration of effluents released via CB-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-10.

=

7.35E-5 sec/mr3 for continuous releases.

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__3 1_23 of 133 (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/m 3) from ATTACHMENT F Table 2.2-8.

=

9.24E-5 sec/m 3 for continuous releases.

(X/Q),Vl

=

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/mr3) from ATTACHMENT F Table 2.2-9.

=

9.24E-5 sec/mr3 for continuous releases.

Ki The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m 3)from ATTACHMENT G Table 2.2-11.

Si

=

From equation [2.1(2)-i].

8.1.2.1.3 BV-2 Maximum Acceptable Release Rate (Skin Exposure)

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

3000 (X/Q)

(Li + 1.1Mi) Si

[2.1(2)-3]

where:

= The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

=

The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

= The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).

1.1 (X/Q)

= Same as in Section 8.1.2.1.2.

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1_3 1_24 of 133 8.1.2.1.4 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:

Qi = Si Qt

[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.

8.1.2.1.5 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:

= 2.12E-3 Qi F

[2.1(2)-5]

where:

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/min x 3.53E-5 ft3/cc).

BV-2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (CR) was determined by:

8.1.2.1.6 CR=

C, Ei

[2.1(2)-6)]

where:

Ei

= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b.

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1 25 of 133 8.1.2.1.7 BV-2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:

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

0.60 x CR HSP=

E-a

[2.1(2)-71 Ei ave where; Ei 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 = -

ave

[2.1(2)-8]

Ei ave 8.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release for VV-2 and CV-2 Ground Releases When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Section 8.1.2.1. In this case, the results of sample analysis are used to determine the appropriate nuclide mix. This calculational method applies when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH Alarm Setpoint based on respective vent flow rate during the following operational conditions:

Batch release of Containment Purge via VV-2.

Batch release of Containment Purge via CV-2.

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__3 1_26 of 133 8.1.2.2.1 BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-2 or CV-2 during purging is determined as follows:

0 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 S T f =

1.6ST[2.1 (2)- 17]

(X/q)

Ki Ci 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/min x 3.53E-5 ft3/cc)

S

=

Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.2.

T

=

Maximum value for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16).(31"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/mi3) from ATTACHMENT M Table 2.3-36.

=

3.32E-4 sec/mi3 (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/m 3) from ATTACHMENT M Table 2.3-37.

3.08E-4 sec/m3

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3 1_27 of 133 Ki

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

Ci

= The undiluted radioactivity concentration of noble gas radionuclide 'iT 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:

6.36ST (X/q) Z(Li +1.1M 1 )C1

[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/min x 3.53E-5 ft3/cc)

Li

=

The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

Mi

= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

(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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3 28 of 133 8.1.2.2.2 BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:

0 The calculated monitor HIGH Alarm Setpoint above background (net uCi/cc) attributed to the noble gas radionuclides is determined by:

f YZCi Ei HSP= F'E

[2.1(2)-19]

HSP-F' Eave where:

f

= The maximum acceptable containment purge flow rate (cfm) determined in Section 8.1.2.2.1.

F'

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

=

53,700 cfm for VV-2

=

59,000 cfm for CV-2 Ci

=

The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.

Ei

-- The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b.

Ei ave

= The CR of equation [2.1(2)-6] divided by the sum of the Ci for the respective mix.

NOTE:

To enable maintaining a constant conversion factor from cpm to uCi/cc in the Digital Radiation Monitoring System software, the "calculated mix" is used rather than the analysis mix to calculate Ei ave above. This does not cause any change in the function of the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.

When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:

ASP = HSP x 0.5

[2.1(2)-20]

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j 29 of 133 8.1.3 BV-1/2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determination.

8.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix For PV-1/2 Elevated Releases The calculated monitor count rate above background (CR), in ncpm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are shown in the following Table:

BV-1/2 ALARM SETPO1NTS FOR ELEVATED RELEASES cpm ABOVE BACKGROUND 60% SITE 30%

(P)PRIMARY*

LIMIT SITE MONITOR UPPER LIMIT (A)ALTERNATE ALARM LOWER MONITOR CR ALARM

" Continuous Release (P)RM-1GW-108B 3.49E7

_ 3.60E5

_ 1.20E5 (A)RM-IGW-109(5) 2.61E7

3.60E5 1 l.20E5

Batch Release Of (P)RM-IGW-108B 3.93E5

_2.36E5

< 1.18E5 BV-I Decay Tanks or (A)RM-1GW-109(5) 7.87E6

_ 3.60E5

< 1.20E5 BV-2 Storage Tanks

IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized:

The setpoints were determined using a calculated mix from the FSAR 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:

0 Continuous release via PV-1/2.

0 Batch release of BV-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 is not shown in the above table. However, if it is necessary to perform a BV-I or BV-2 Containment Purge via this release point, the alarm setpoint shall be calculated in accordance with Section 8.1.3.2.

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3 30 of 133 8.1.3.1.1 BV-1/2 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:

0 The gaseous source terms that are representative of the "mix" of the gaseous effluent were evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. The gaseous source terms can be obtained from ATTACHMENT A Tables 2.1-la. and 2.1-lb.

The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was calculated by:

Si - A i YAi

[2.1-9]

where:

Ai

=

The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-1a and 2.1.lb.

BV-1/2 Maximum Acceptable Release Rate (Whole Body Exposure) 8.1.3.1.2 The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was determined by:

Qt =500 Zvi Si

[2.1.10]

where:

Vi = The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrem/year/uCi/sec) from ATTACHMENT G Table 2.2-12.

S = From equation [2.1-9]

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3 31 of 133 8.1.3.1.3 BV-1/2 Maximum Acceptable Release Rate (Skin Exposure)

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

3000 Qt=

[2.1-11]

S[Li (X/Q)pv + 1. 1 Bi]Sj where:

Li

= The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

(X/Q)p,

=

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/m 3) from ATTACHMENT F Table 2.2-6.

= 2.3 1E-6 sec/m 3 (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/mr3) from ATTACHMENT N Table 2.3-3 8.

= 1.07E-5 sec/mr3 (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.

8.1.3.1.4 BV-1/2 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 individual noble gas radionuclide in the gaseous effluent was determined by:

Qi = Si Qt

[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.

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1_3 32 of 133 8.1.3.1.5 BV-1/2 Maximum Acceptable Concentrations (Individual Radionuclide)

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

Ci = 2.12E-3 Qj

[2.1-13]

F where:

2.12E-3 =

Unit conversion factor (60 sec/min x 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.

8.1.3.1.6 BV-1/2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide. (CR) was determined by:

CR=

Ci Ei

[2.1-14]

where:

Ei

= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.

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

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

HHSP = 0.60 x CR

[2.1-15]

" The monitor HIGH Alarm Setpoint above background (ncpm) was determined by:

HSP = 0.30 x CR

[2.1-16]

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1_3 1_33 of 133 8.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release For PV-1/2 Elevated Releases The following calculation method applies to gaseous releases via the PV-1/2 Gaseous Waste/Process Vent when the "calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the BV-1/2 Gaseous Waste Gas Monitor (RM-GW-108B) or alternate (RM-IGW-109 CH 5) during the following operational conditions:

Continuous release via PV-1/2.

Batch release of BV-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.

8.1.3.2.1 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.

0 The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by:

1.06S

[2.1-21]

zi C1 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/min x 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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1_3 1_34 of 133 CQ 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.

0 Based upon the skin exposure limit, (f) is calculated by:

6.36S f [Li (X/Q)p+

B

+I

]C,

[2.1-22]

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/nin x 3.53E-5 ft3/cc)

Li The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m 3) from ATTACHMENT G Table 2.2-11.

(X/Q)p, 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/m 3) from ATTACHMENT F Table 2.2-6.

2.31E-6 sec/m 3

(X/q)p, 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/mi3) from ATTACHMENT N Table 2.3-38.

1.07E-5 sec/m 3 Bi 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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3

__35 of 133 8.1.3.2.2 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:

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

f ZCi E1 HHSP -

F'

[2.1-23]

where:

f

=

The maximum acceptable gaseous discharge flow rate (cfm) 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.

Ei

=

The detection efficiency of the respective monitor (RM-1GW-108B) or (RM-IGW-109 CH 5) for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.

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

HSP = HHSP x 0.5

[2.1-24]

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3 36 of 133 82 Compliance With 10 CFR 20 Dose Rate Limits (ODCM CONTROL 3.11.21) 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 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 (3.1.3.1) the following equations are used to show compliance with ODCM CONTROL 3.11.2.1.a.

S[ViQs + Ki(X/Q)v Q]< 500 mrem/yr

[2.2-1]

S((Li(X--Q) +1.1B,]Qjý +[Li +1.1Mi](X/Q)v Qv]< 3000mrem/yr

[2.2-2]

j where:

Ki

=

The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrem/year/uCi/m 3.

Li

=

The skin dose factor due to beta emissions for each identified noble gas radionuclide "i", mreem/year/uCi/m 3.

Mi

=

The air dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrad/year/uCi/m3.

Vi

=

The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrem/year/uCi/sec.

Bi

=

The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad/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.

Qiv

=

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

(X/Q), = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/m3).

(X /Q )v = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/mr3).

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3 37 of 133 At the Beaver Valley site gaseous releases may occur from the following Release Points (RP's) 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)

RP 2 & 5. The BV-i 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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1 3 38 of 1 33 8.2.1.1 Total Body Dose Rate (All Release Points)

Y-ViQ i

+ Y-i Ki [(X/Q)cv Qi

+ (X/Q)vv Qi

+ (X/Q)cv Qi

+ (X/Q)vv i

pv Qv1 vv]Q cv2 Qi

+ (X/Q)tv Q.it2 + (X/Q)cb Qi

+ (X/Q)dv Qi

+ (X/Q)wv Qi

]

v2cb2 dv2 wv2

< 500 mrem/yr

[2.2-3]

8.2.1.2 Skin Dose Rate (All Release Points) 4-L.(x/Q) v+I.1B. Q.

+/-X[L.+1.IM.][(X Q)

+(X/Q)v Q.

+

v p1

I I 'XQ cvQ.

VV jLpv i

vv 1 cv2 (X/Q)cv Qi

+ (X/Q)vv Qi

+ (X/Q)tv Qi

+ (X/Q)cb Qi

+ (X/Q)dv cv2 vv2 tv2 cb2 Qi

+ (X/Q)

Qi

] -< 3000 mrem/yr

[2.2-4]

dv2 wv2 where:

Qi

=

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

pv Qicvi

=

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

=

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

cv2 Qi

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

vvl Qi

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

vv2 Qi

=

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

tv2 Qi

=

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

eb Qi

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

dv2

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1_3 39_of_133 Qi

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

wv2 (X/Q )pv

= Highest calculated annual average relative concentration for releases from the PV-1/2, sec/m 3.

(X/Q )cv

= Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m3.

(X/Q )v

=

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

(X/Q )v

= Highest calculated annual average relative concentration for releases for TV-2, sec/m 3.

(X/Q )cb

= Highest calculated annual average relative concentration for releases for CB-2, sec/m 3.

(X/Q )dv

=

Highest calculated annual average relative concentration for releases for DV-2, sec/m 3.

(X/Q)wV

=

Highest calculated annual average relative concentration for releases for WV-2, sec/m 3.

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 of ODCM CONTROL 3.11.2.1.a is 0.35 miles NW. Inserting the appropriate X/Q's from ATTACHMENT F Tables 2.2-4 through 2.2-10 for this location, Equations [2.2-3] and

[2.2-4] become:

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1_3 1_40 of 133 8.2.1.3 Total Body Dose Rate (at 0.35 Miles NW)

ZVQ.+

Y Ki [9.24E - 5 Q i i ipv cvl

+1.03E-4Q.i vv

+ 9.24E - 5 Qi dv 2

+ 9.24E - 5 Qi

+

2 cv 1.03E - 4 Qi

+ 7.35E-5Q i

+ 9.24E-5Q 1

+

2 2

vv tv 7.35E-5 Qi'cb2 j < 500mrem/yr

[2.2-51 8.2.1.4 Skin Dose Rate (at 0.35 Miles NW)

Z[7.OE-10L.

+1.1 1B.IQ i

Z[Li + 1.IM.]+9.24E-5 Q.

+1.03E -4 1

' cv pv I

Qi

+9.24E-5Q.i

+1.03E-4Qi vi CV

+7.35E-5Q.

+9.24E Qi5v2-Qidv2

+

9.24E - 5 Qiwv2 + 7.35E -5 Qicb2 ] -< 3000 mrem/yr

[2.2-6]

For Release Mode 4, the controlling location is 0.75 miles N. 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:

8.2.1.5 Total Body Dose Rate (at 0.75 Miles N)

ZViQi

+ZKi [3.95E-6Q.

+4.99E-6Qvv

+ 3.95E-6Q.i i

pv 1

CV1V

+ 4.99E -

6Qi

+ 4.26E-6Q i vv 2

+3.95E-6Qi dv2

+ 3.95E - 6 Qi

+ 4.26E - 69Qi cb 2 I 2

2 tv

%Vv

_< 500 mrem/yr 8.2.1.6 Skin Dose Rate (at 0.75 Miles N)

[2.2-7]

Y [2.31E-6 L ++/-1.IB.JQ, + [Li. + 1.1M.J[3.95E-6Qi i

pv 1

I cv

+4.99E-6Qi1 vv

+

3.95E - 6 Qi 12 cv

+ 4.99E-6Q i

+ 4.26E-6Qi tv

+ 3.95E-6Qi

+ 3.95E-dv 2

VV 6Qi

+ 4.26E - 6 Q,

] -< 3000 mrem/yr

[2.2-8]

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3 41 of 133 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 [2.2-5 through 2.2-8].

The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GAS 1BB (similar to NUREG-0017.(3 134 ) Inputs were based on operating modes of the respective plants. The code inputs utilized are presented in 1/2-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. ATTACHMENT F Tables 2.2-4 through 2.2-10 present the long-term annual average (X/Q) values for all Release Points to the special locations presented in ATTACHMENT E Table 2.2-3. A description of their derivation is provided in 1/2-ODC-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-I and CV-2. In Release Modes 2 and 3, the dominant release is a Containment Purge from the VV-1 or VV-2.

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3 1_42 of 133 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 [2.2-5] through [2.2-8] to show compliance with ODCM CONTROL 3.11.2.1.2, are presented in Table 2.2-11.

Values taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1'(3'135) were multiplied by 1E6 to convert picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.

Values for Vi and Bi 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:

Kjk faiUa EI

[2.2-9]

rdjklI u

where:

The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (uj) and atmospheric stability class "k" for a particular wind direction.

K

= A numerical constant representing unit conversions.

(260 mrad)(radians) (m3) (transformation) 16 sectors (sec)(Mev)(Ci) 1271 radians]

LIE-6 Ci 3.15E7 sec 1 uci I [

yr.I

=

2.1 E4 mrad (mi3) (transformation)/yr(Mev)(uCi).

rd

= The distance from the release point to the receptor location, meters.

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3 43-of 133 uj

=

The mean wind speed assigned to the "j" th wind speed class, meters/sec.

fjk

=

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

Ali =

The number of photons of energy corresponding to the "I" th energy group emitted per transformation of the "i" th radionuclide, number/transformation.

Ei

= The energy assigned to the "I" th energy group, Mev.

Ua

=

The energy absorption coefficient in air for photon energy Hl, meters -1.

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

Kf A liu aElIV - UTTd V

K jk Ai a

u

[2.2-10]

i r djkl u

where:

UT

= The tissue energy absorption coefficient for photons of energy El, cm 2/gm.

Td

= The tissue density thickness taken to represent the total body dose (5gm/cm 2).

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 of 1-131, 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,(131) the following basic equation is used to show compliance with ODCM CONTROL 3.11.2.1.b:

z PiT [(X/Q)X Qi, + (X/Q), Qv

< 1,500 mrem/yr

[2.2-11]

where:

Pi

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

mrem/yr per uCi/m3.

Qis

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

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1_3 1_44 of 133 Qiv

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

(X/Q), = 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.

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.

IT ~

V pv

+ (X/Q)cv QicvI +(X/Q)vv Qi vv I

+ (X/Q)cv Qi c cv2 + (X/Q)vv (X/Q)tv Qi tV2 + (X/Q)cb Qicb2 + (X/Q)dv Qi dv 2 + (X/Q)wv Q.i

] < 1500 mrem/y$

[2.2-12]

where:

(X/Q)Pý (X/Q)CV

= Highest calculated annual average relative concentration for releases from PV-1/2, sec/m 3.

= Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m 3.

= Highest calculated annual average relative concentration for releases from VV-1 and VV-2, sec/m 3.

= Highest calculated annual average relative concentration for releases 3

from TV-2, sec/mr

= Highest calculated annual average relative concentration for releases 3

from C13-2, sec/rn (X/Q),"

(X/Q)c~b

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__3 __45 of 133 (X/Q)dv = Highest calculated annual average relative concentration for releases from DV-2, sec/m 3.

(X/Q),

= Highest calculated annual average relative concentration for release from WV-2, sec/m3.

Qi

= Long-term release rate of radionuclide "i" from PV-1/2, uCi/sec.

pv Qi cv

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

Qi

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

'cv2 Qi

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

vv2 Q.

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

I tv2 Q.

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

'cb2 Q.

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

'dv2 Qi

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

'wv2 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.

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__3 1_46 of 133 Values of the organ dose parameters, Pi, were calculated using methodology given in NUREG-0133.(13 3 1) For the child age group, the following equation was used for all nuclides. The Pi, values are presented in ATTACHMENT H Table 2.2-13.

Pi, = 3.7E9 DFAi,

[2.2-13]

where:

3.7E9 =

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

DFAiT =

The organ inhalation dose factor for a child from Table 6 of NUREG-0172, 3 13 6 ) 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.

Equation [2.2-12] becomes:

EP. [7.OOE-10 Qi

+ 9.24E-5 Q.

ipv lcvl +1.03E-4Qi vv 1 +7.35E-5 Q.ltvlI

+

9.24E -

Qicv2 + 1.03E-4Q.'vv2 +7.35E-5Qitv2 +7.35E-5Q.icb2 +9.24E-5Q.'dv2 + 9.24E-5 Q i wv2 ] < 1500 mrem/yr

[2.2-14]

8.2.2.1 Determination of Controlling Location The determination of the controlling location for implementation of ODCM CONTROL 3.11.2.1.b for radioiodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Equation [2.2-12] results in the respective equations for each Release Mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.

In the determination of the controlling site boundary for each Release Mode, the highest 2 site boundary X/Q values for each Release Point were utilized in conjunction with the radionuclide mix and the release rate for each Release Point to determine the controlling location.

The Pi, values are presented in ATTACHMENT H Table 2.2-13.

The X/Q values in Equation [2.2-14] were obtained from ATTACHMENT F Tables 2.2-4 through 2.2-10.

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__3 1_47 of 133 A description of the derivation of the X/Q values is provided in 1/2-ODC-3.01.

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

(Gaseous)

At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radwaste system. The effluent from both units are mixed and discharged from a common Release Point, the PV-1/2 Gaseous Waste/Process Vent, at the top of the Unit 1 Cooling Tower. The resulting dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception would be a Containment Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5.

8.3.1 Dose Due To Noble Gases 8.3.1.1 Cumulation Of DosesSection II.B.I 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,(313]) the air dose limits in the unrestricted area due to noble gases released in gaseous effluents are defined by the following equations:

8.3.1.1.1 Gamma Radiation Quarter Limit 3.17E-8Z YMi [(X/Q) vQiv +(X/q)vqivJ+[BIQis + biqisj 5 5mrad

[2.3-1]

i 8.3.1.1.2 Beta Radiation Quarter Limit 3.17E-8Y Ni [(X/Q)

Qiv +(X/q)vqiv + (X/Q)sQis +(X/q)sqis] < 10mrad [2.3-2]

8.3.1.1.3 Gamma Radiation Year Limit 3.17E-8

[Mi[(X/Q)v Qiv+(X/q)vqiv] +[BiQis +biqis)) -<ý 10mrad 8.3.1.1.4 Beta Radiation Year Limit 3.17E-8Y N

+ (X/q)vqiv + (X/Q)sQis + (X/q)qS] _< 20mrad

[2.3-4]

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3 1_48 of 333 8.3.1.1.5 Gamma Radiation Projection Averaged Over 31 Days 3.17E-8 2 [Mi [(X/Q)v Qiv + (X/q)vqiv + [BiQis +biq is< 0.2 mrad

[2.3-5]

i 8.3.1.1.6 Beta Radiation Projection Averaged Over 31 Days 3.17E-8 Y Ni [(X/Q)vQiv +(X/q)vqiv + (X/Q)sQis +(X/q)sqisj-<0.4mrad

[2.3-6]

i where:

Mi

= The air dose factor due to gamma emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3).

Ni

=

The air dose factor due to beta emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3).

(X/Q),

=

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/mr3).

(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/mi3).

(X/Q)5

=

The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack releases greater than 500 hrs/year (sec/m 3).

(X/q)5

=

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/m 3).

qis

=

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

qiv

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

Qis

= Release of noble gas radionuclide "i" in gaseous effluents for long-term free standing stack releases greater than 500 hrs/year (uCi).

Qiv

= Release of noble gas radionuclide "i" in gaseous effluents for long-term vent releases greater than 500 hrs/year (uCi).

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ODM:GAEOS FFUET 49 of 133 Bi

= The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide 'T' accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).

bi

=

The constant for short-term releases (equal to or less than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).

3.17E-8 = The inverse of the number of seconds in a year.

NUREG 0133(3.11) permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions. This special consideration is applied in Equations [2.3-1] through

[2.3-6], however, a summary of the "real time" meteorological data coupled with the corresponding releases shall be included in the Annual Radioactive Effluent Release Report.

Short-term releases are also evaluated annually in computer codes technically consistent with XOQDOQ and GASPAR for inclusion in the Annual Radiological Environmental Report.

The incorporation of this option and the Release Modes of ATTACHMENT I Table 2.3-1 results in the following equations to show compliance with 10 CFR 50 for the calendar quarter or year.

8.3.1.1.7 Gamma Radiation Dose Equation 3.17E-8 Y[Mi [(X/Q)cvQi

+ (X/Q)vvQi

+ (X/Q)cb i

+(X/Q)dvQi

+

i cv vv cb dv (X/Q)wvQi

]+0.5B5 Qi

]

[2.3-7]

Wv pv

< 0.2 mrad (per 31 days), or

< 5.0 mrad (per quarter), or

<10.0 mrad (per year)

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1 3 50 of 133 8.3.1.1.8 Beta Radiation Dose Equation 3.17E-8.Ni [(X/Q)cvQi

+(X/Q)wQi

+ (X/Q)cbQi

+(X/Q)dvQi

+

1 cv vv cb dv (X/Q)

Q

+.5(X/Q)pv Qipv ]

[2.3-8]

wv

< 0.4 mrad (per 31 days), or

< 10.0 mrad (per quarter), or

< 20.0 mrad (per year) where:

(X/Q)'v Annual average relative concentration for releases from CV-1 and CV-2 (sec/m3n).

(X/Q),, = Annual average relative concentration for releases from VV-1 and VV-2 (sec/mr3).

(X/Q)pv = Annual average relative concentration for releases from PV-1/2 (sec/m 3).

(X/Q)tv = Annual average relative concentration for releases from TV-2 (sec/mr3).

Qi

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

ev Qi

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

vv Qp

=

Release of radionuclide iT' from PV-1/2 (uCi).

PV Q

=

Release of radionuclide "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).

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3 51 of 133 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-8Z[Mi[9.24E-5Qi

+1.03E-4Qi

+7.35E-5Qi

+

i cv vv tv cb 9.24E-5QQ

+9.24E-5Qi

]+0.5BiQi

[2.3-9]

dv Wv pv

< 0.2 mrad (per 31 days), or

< 5.0 mrad (per quarter), or

< 10.0 mrad (per year) 8.3.1.1.10 Beta Radiation Dose Determination 3.17E-8YNi[9.24E-5Qi

+1.03E-4Qi

+7.35E-5Qi

+

i cv vv tv cb 9.24E-5 Qi

+9.24E-5 Qi

+(0.5)7.OE-1OQi

]

[2.3-10]

dv wv pv

< 0.4 mrad (per 31 days), or

< 10.0 mrad (per quarter), or

< 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-3.01 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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1_3 1

52_of133 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 ATTACHMENT 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 Ni, which were used in the determination of the controlling location and which are to be used by BV-I and BV-2 in Equations [2.3-9] and

[2.3-10] to show compliance with 10 CFR 50 were presented in ATTACHMENT G Table 2.2-11. Values taken from Table B-I of Regulatory Guide 1.109, Revision 1(.13.) were multiplied by 1E6 to convert from picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.

In determination of the controlling location for Release Modes 1, 2, 3, and 4, ATTACHMENT F Tables 2.2-4 through 2.2-7 are utilized for X/Q values.

The Bi values to be utilized are the same values which were presented in ATTACHMENT G Table 2.2-12. A description of the derivation of the various X/Q values is presented in 1/2-ODC-3.01.

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3 53 of 133 The following relationship must hold for BV-1I or BV-2 to show compliance with ODCM CONTROL 3.11.2.2:

For The Calendar Quarter Dy < 5.0 mrad

[2.3-11]

Do < 10 mrad

[2.3-12]

For The Calendar Year Dy < 10 mrad

[2.3-13]

Dp < 20 mrad

[2.3-14]

where:

Dy =

The air dose from gamma radiation (mrad).

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

The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Equations

[2.3-11 ] through [2.3-14] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations.

In addition, ODCM CONTROL 3.1.2.4 requires that the gaseous radwaste system must be used to reduce radioactive materials in that waste when projected doses from each reactor unit when averaged over 31 days exceed any of the following:

Dy < 0.2 mrad

[2.3-15]

Dp < 0.4 mrad

[2.3-16]

8.3.1.2 Proiection Of Doses (Noble Gas)

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

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3 54 of 133 using Equations [2.3-9] and [2.3-10] as appropriate. The 31-day dose projection shall be performed according to the following equations:

8.3.1.2.1 When Including Pre-Release Data, D31 =-A+B (31) + C

[2.3-17]

T 1

8.3.1.2.2 When Not Including Pre-Release Data, D31 =[A] (31) + C

[2.3-18]

where:

D31

=

Projected 31 day dose (mrad).

A

=

Cumulative dose for quarter (mrad).

B

= Projected dose from this release (mrad).

T

= Current days into quarter.

C

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

8.3.2 Dose Due To Radioiodines And Particulates 8.3.2.1 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,( 3 13 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:

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__3 1_55 of 133 8.3.2.1.1 Radioiodines and Particulates Month, Quarter, and Year Limits 3.17E-8.R. ir [WsQiS +wsqis + WvQiv + wvqiv]

< 0.3 mrem (per 31 days), or

[2.3-19]

< 7.5 mrem (per quarter), or

< 15.0 mrem (per calendar year) where:

Qis

=

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

Qiv

=

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

qis

=

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

qiv

=

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

W,

=

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/mr3 for the inhalation pathway, (W/Q)s.

= meters 2 for the food and ground plane pathway, (D/Q)s.

Wv

= The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs/yr.

=

sec/mr3 for the inhalation pathway, (X/Q )v.

=

meters2 for the food and ground plane pathway, (D/Q)v.

Ws

=

Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases equal to or less than 500 hrs/yr.

sec/mr3 for the inhalation pathway, ( W/q )s.

=

meters-2 for the food and ground plane pathway, (D/q)s.

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1_3 1_56 of 333 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/m 3 for the inhalation pathway, (X/q)v.

=

meters2 for the food and ground plane pathway, (D/q),.

3.17E-8 =

The inverse of the number of seconds in a year.

Ri,

=

The dose factor for each identified radionuclide "i" for the organ "`" of interest (mrem/yr per uCi/sec per m2 or mrem/yr per uCi/m3).

Radionuclides and particulates may be released from any of the BV-I and BV-2 Release Points in the Release Modes identified in ATTACHMENT I Table 2.3-1. As described previously in Section 8.3.1.1, NUREG 0133(3131) permits use of long-term annual average dispersion calculations (which with the release modes of Table 2.3-1 results in the following equations) to show compliance with ODCM CONTROLS 3.11.2.3 and 3.11.2.4. For a particular organ, Equation [2.3-19] becomes:

8.3.2.1.2 Radioiodines and Particulates Dose Equation 3.17E-8 R*Ri. [0.5 W pvQi

+ WcvQii W+

WtvQi

+ W cbQi

+

I p

v cv vv tv cb WdvQi

+Wwv Qi

]

[2.3-20]

dv wV

< 0.3 mrem (per 31 days), or

_ 7.5 mrem (per quarter), or

_ 15.0 mrem (per calendar year) where:

0.5 Wpv

=

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 Wcv

=

Dispersion parameter for releases from CV-1 and CV-2.

W,*

= Dispersion parameter for releases from VV-1 and VV-2.

Wt,

= Dispersion parameter for releases from TV-2.

Wcb

= Dispersion parameter for releases from CB-2.

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3 57 of 133 Wdv

= Dispersion parameter for releases from DV-2.

Ww*

= Dispersion parameter for releases from WV-2.

Qi

=

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

pv 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 Qi

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

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.

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3 58 of 133 8.3.2.1.2.1 In determining the dose at a particular location, dispersion parameter W is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q.

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

Radioiodines and Particulates Dose Determination 3.17E-8 Z((R.

+R.

][0.5W Q

+WcvQi

+

i rt3 riM I V R

]

W pvcvcv WvvQ ivv + WtvQitv +WcbQicb + WdvQidv + WwvQi. ]

+ R.rrl [0.5 (X/Q)pv Qipv + (X/Q)cv Qicv + (X/Q)vv Qivv +

(X/Q) tvQi

+(X/Q)cbQi

+ (X/Q)dvQi tv cb dv Qi

]

+ (X/Q)wv I

[2.3-21]

< 0.3 mrem (per 31 days), or

< 7.5 mrem (per quarter), or

< 15.0 mrem (per year) where:

R.1"tG R.

ITM R.

IT V R.

ITB R.

ITI

= Dose factor for an organ "T" for radionuclide "i" for the ground plane exposure pathway (mrem/yr per uCi/sec per m2).

= Dose factor for an organ "T" for radionuclide "i" for either the cow milk or goat milk pathway (mrem/yr per uCi/sec per m2

=

Dose factor for an organ "T" for radionuclide "i" for the vegetable pathway (mrem/yr per uCi/sec per m2).

= Dose factor for an organ "T" for radionuclide "i" for the meat pathway (mrem/yr per uCi/sec per m-2).

= Dose factor for an organ "T" for radionuclide "i" for the inhalation pathway (mrem/yr per uCi/m 3).

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3 59 of 133 It should be noted that Wpv, Wcv, Wvv, Wyt Wcp, Wda, and Wv in Equation

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

Values of the dose factor, Ri, were calculated using the methodology of NUREG-0133.(' 3 1 ) The following equations were used for all nuclides except tritium:

8.3.2.1.2.2 Dose Factors For Inhalation Pathway R.

= K' (BR)a(DFAit)a il'I

= mrem/yr per uCi/m 3

[2.3-22]

where:

K'

= A constant of unit conversion (1E6 pCi/uCi).

(BR)a

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

(DFAi,)a

=

Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem/pCi). Inhalation dose factors (DFAi) by organ for the various age groups are given in Table E-7 through E-10 of Regulatory Guide 1.109, Rev. 1(313-) or Tables 5 through 8 of NUREG-0 172 for all nuclides except Se-75. 3.13 6)

Se-75 DFAit were provided by ABS Consulting and were derived from MACCS2(31 3 16 ), FGR 11/12 (31317 and 18) and ORNL-4992(3.319) using conversion factors for the adult pathway only.

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.)

Age Group(a)

Breathing Rate (m3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000

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3 60 of 133 8.3.2.1.2.3 Dose Factors For Ground Plane Pathway R.

= KK" (SF)DFGi,[(1 - eXit)/Xil ITG

= m2 -mremryr per uCi/sec

[2.3-23]

where:

K'

= A constant of unit conversion (1E6 pCi/uCi).

K"

=

A constant of unit conversion (8760 hr/year).

Xi

=

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

t=

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

DFGiT

=

The groundplane dose conversion factor for organ "`" for the "i" th radionuclide (mrem/hr per pCi/m2). A tabulation of DFGi, values is presented in Table E-6 of Regulatory Guide 1.109.(13.5) for all nuclides except Se-75.(3 136)

Se-75 DFGi, were provided by ABS Consulting and were derived from MACCS2(31 3 16), FGR 11/12(313.17 and 18) and ORNL-4992 (3.3.19) using conversion factors for the adult pathway only.

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' 35 )

8.3.2.1.2.4 Dose Factors For Cow Milk or Goat Milk Pathway R.iM = K' QF(Uap) Fm(r)(DFLi.)a -fpf" + ( - fPfsIe-iTh-e w m2 -mrem/yr per uCi/sec

[2.3-24]

where:

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).

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1_3

_61 of 1333 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.

(DFLi,)a

=

The maximum organ ingestion dose factor for the "Ti th radionuclide for the receptor in age group "a" (mrem/pCi).

Ingestion dose factors (DFLi,)a for the various age groups are given in Table E-l I through E-14 of Regulatory Guide 1.109("1.3-5) or Tables I through 4 of NUREG-0172.(3136) for all nuclides except Se-75.(3.1 36 ) Se-75 DFLi, were provided by ABS Consulting and were derived from MACCS2 3(

13 16 ), FGR 11/12(3'1317 and 18) and ORNL-4992(31319) using conversion factors for the adult pathway only.

Ai

=

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

k'w

= 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).

tf

= The transport time from pasture, to animal, to milk, to receptor (sec).

th

= The transport time from pasture, to harvest, to animal, to milk, to receptor (sec).

fp

=

Fraction of the year that the animal is on pasture (dimensionless).

fs

=

Fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless).

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1 3 62 of 133 Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.109.(3135)

Parameter r (dimensionless)

Fm (days/liter)

Uap (liters/yr) - infant child teen adult (DLFi,)a (mrern/pCi)

Yp (kg/m2)

Ys (kg/m2)

Value 1.0 for radioiodine 0.2 for particulates each stable element RG. 1.109 Table E-15 E-15 E-1 (cow milk)

E-2 (goat milk) 330 330 400 310 E-5 E-5 E-5 E-5 each radionuclide E-11 to E-14 0.7 2.0 tf (seconds) th (seconds)

QF (kg/day) 1.73E5 (2 days) 7.78E6 (90 days) 50 E-15 E-15 E-15 E-15 E-3 0.5 1.0 f,

For goat's milk, all values remain the same except for QF, which is 6 kg/day.

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3 63 of 133 8.3.2.1.2.5 Dose Factors For Meat Pathway QF(U ap) Fr)(fP

(

fpfs

( -f

)e-ithi Ri.

K

" + k f (r)(DFLiT)a Y

jY

= m2 -mrem/yr per uCi/sec

[2.3-25]

where:

Ff

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

Uap

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

tf

=

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 Ff which is obtained from Table E-1. Parameter tf is obtained from Table E-15, and Uap is obtained from Table E-5. These values, as obtained from Regulatory Guide 1.109,(31"35) are as follows:

Parameter Value RG-1.109 Table Ff (days/kg) each stable element E-1 tf (seconds) 1.73E6 (20 days)

E-15 Uap (kg/yr) - infant 0

E-5 Child 41 E-5 Teen 65 E-5 Adult 110 E-5

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3 64 of 133 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

8.3.2.1.2.6 Dose Factors For Vegetation Pathway R

=K'

, (r) 1 (DFL )

fULfL-e -itL

+ Uf e -ith R.v Yv1('

ira a

a g i

= m2 -mrem/yr per uCi/sec

[2.3-26]

where:

K'

=

A constant of unit conversion (1E6 pCi/uCi).

UL U a

=

The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).

Us= 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).

Y,

= The vegetation area density (kg/m2).

all other factors are defined previously.

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3 65 of 133 Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109.(1.3.5)

Parameter r (dimensionless)

(DFLita (mrem/pCi)

U L (kg/yr) -infant a

Child teen adult US (kg/yr) - infant a

child teen adult fL (dimensionless)

Fg (dimensionless)

Value 1.0 for radioiodines 0.2 for particulates each stable element RG-1.109 Table E-15 E-15 E-1 1 to E-14 0

26 42 64 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 0

520 630 520 1.0 0.76 tL (seconds) th (seconds)

Yv (kg/mr2) 8.6E4 (I day) 5.18E6 (60 days)

E-15 E-15 E-15 E-15 E-15 2.0

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3 66 of 133 As 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 1/2-ODC-2.04, as follows:

8.3.2.1.2.7 Tritium Dose Equation 3.17E - 8 (R m + RTrv + RTr B + RTr, ) [0.5 (X/Q)pv QTpv + (X/Q)cv QT cv

+

(X/Q)vQT

+ (X/Q)tvQT

+ (X/Q)cbQT vv tv cb + (X/Q)dv Q

+ (X/Q)wv QC I

.dv w~v

[23-27].

where:

RT-M =

Dose factor for organ "-r" for tritium for the milk pathway (mrem/yr per uCi/Mr3).

RT-tv = Dose factor for organ "t" for tritium for the vegetable pathway (mrem/yr per uCi/m 3).

RTTB = Dose factor for organ "r" for tritium for the beef pathway (mrem/yr per uCi/m 3).

RTrI

= Dose factor for organ "t" for tritium for the inhalation pathway (mrem/yr per uCi/m 3).

Equation [2.3-27] is used to show compliance with 40 CFR 190, as discussed in 1/2-ODC-2.04.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RT-M is based on [X/Q]:

8.3.2.1.2.8 Tritium Dose Factors For Milk Pathway RTTM = K'K" FmQFUap(DLFi-t)a[0.75(0.5/H)]

= mrem/yr per uCi/m 3

[2.3-28]

where:

K"

= A constant of unit conversion (1000 gm/kg).

H

= Absolute humidity of the atmosphere (8 gm/m 3).

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1_3 67 of 133 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 Ri-cM.

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

8.3.2.1.2.9 Tritium Dose Factors For Vegetation Pathway R

v = K'K"[UafL +

]Ufg (DFLi )a [0.75(0.5/H)]

= mrem/yr per uCi/m 3

[2.3-29]

where all terms have been defined above.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RTtB is based on [X/QJ:

8.3.2.1.2.10 Tritium Dose Factors For Beef Pathway RT

= K'K"FfQFU (aDFLi

) [0.75(0.5/H)]

B-3 ap itra

= mrem/yr per uCi/m3

[2.3-30]

where all terms have been defined above.

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1_3 1_68 of 133 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 I 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 Dose Determination 3.17E-8 Zi ((R iG + Ri.rv ] [(0.5)4.22E-10 QiPV + 1.56E-8 Qcv + 1.56E-8 Q.+l.5-8.

+1.55E-8Q

+1.56E-8Q

+1.56E-8 Qivv + 1.55E-8Qitv Qicb Qidv Qiw. ] + Ri- [(0.5) 7.30E - 9 Q.PV + 2.OOE - 5 Qicv + 2.71E - 5 Qi.

+ 2.22E-5Qi.tv + 2.22E-5 Qicb + 2.OOE-5 Qidv + 2.OOE-5 Qiw]

< 0.3 mrem (per 31 days), or

[2.3-31]

< 7.5 mrem (per quarter), or

<15.0 mrem (per year)

For tritium, for purposes of implementation of 40 CFR 190, as discussed in 1/2-ODC-2.04, Equation [2.3-28] reduces to:

3.17 E-8[RTTv +RTr ][(0.5)7.30E-9Qi

+2.OOE-5Qi.

+2.71E-V I

PV icy 5Qi.v + 2.22E-5Qitv + 2.22E-5 Qicb +2.OOE-5Qidv +

2.OOE - 5 Qi.v ]

[2.3-32]

8.3.2.1.4 Determination of Controllin2 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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3 69 of 133 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 2.2-2a and 2.2-2b as a function of Release Mode and Release Point. For the ground plane exposure pathway, all radionuclides (excluding H-3 and C-14) were considered in determination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling location.

In determination of the controlling location for each Release Mode, all of the exposure pathways, as presented in ATTACHMENT E Table 2.2-3, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations.

For determination of the controlling location, the highest D/Q and X/Q values for each Release Point and Release Mode for the vegetable garden, cow milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and Release Points of ATTACHMENT D Tables 2.2-2a and 2.2-2b Based upon these calculations, it was determined that the controlling location for Release Modes 1 through 4 is the residence (vegetable garden)/child pathway.

For Release Modes I through 4, the controlling Release Point and mix is VV-1 and VV-2.

ATTACHMENT J Tables 2.3-2 through 2.3-20 present Ri values for the total body, GI-LLI, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.

These values were calculated using the methodology described in NUREG-0133(31 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/Q's, 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 1/2-ODC-3.01.

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1_3 70 of 133 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:

D, < 7.5 mrem to any organ

[2.3-33]

For The Calendar Year:

D, < 15 mrem to any organ

[2.3-34]

where:

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

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

[2.3-33] and [2.3-34] are exceeded, a Special Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.3.a must be filed with the NRC at the identified locations.

8.3.2.2 Projection Of Doses (Radioiodines And Particulates)

Doses due to gaseous releases from BV-I or BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of radioiodines 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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3 71 of 133 8.3.2.2.1 When Including Pre-Release Data, D 3 1 =[AB 1(31) + C

[2.3-35]

T 8.3.2.2.2 When Not Including Pre-Release Data, D31 = [A](31)+C

[2.3-36]

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 effluent Release Points is provided as ATTACHMENT P Figure 2.4-2. Since the concept of a shared gaseous radwaste system is used, then gaseous waste generated can be stored, processed, and discharged from either BV-I or BV-2.

8.4.1 BV-1 Gaseous Radwaste System Components 8.4.1.1 BR-1EV-2A/2B: Degasifiers There are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.

8.4.1.2 GW-1E-1A/1B: Waste Gas Chillers There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.

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__3 72 of 133 8.4.1.3 GW-1TK-3A thru 3D: Gaseous Waste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.

8.4.1.4 GW-1FL-5A/5B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.

8.4.1.5 GW-1C-1A/1B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters.

8.4.1.6 GW-ITK-2: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.

8.4.1.7 GW-1TK-1A thru 1C: Waste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.

8.4.1.8 RM-1GW-108 And RM-1GW-109: Gaseous Effluent Radiation Monitors There are redundant Radiation Monitors on the combined PV-1/2 Gaseous Waste/Process Vent release path. These Radiation Monitors continuously analyze gaseous waste as it is being discharged. Gaseous Monitor RM-IGW-108B is an off-line gamma scintillator, while RM-1GW-109 Channel 5 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 I-1GW-108B is received, it automatically terminates the discharge by closing an isolation valve downstream of the Decay Tanks.

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1 73 of 133 8.4.2 BV-2 Gaseous Radwaste System Components 8.4.2.1 2BRS-EV21A/21B: Degasifiers There are four Degasifiers (two at Unit I and two at Unit 2). They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.

8.4.2.2 2GWS-E21A/21B: Waste Gas Chillers There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.

8.4.2.3 2GWS-TK22A thru 22D: Waste Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit I and four at Unit 2). The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.

8.4.2.4 2GWS-FLT24A/24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Waste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.

8.4.2.5 2GWS-C21A/21B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters.

8.4.2.6 2GWS-TK21: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.

8.4.2.7 2GWS-TK25A thru 25G: Gaseous Waste Storage Tanks There are seven Storage Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Storage Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.

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1 74 of 133 8.4.2.8 RM-IGW-108 And RM-1GW-109: Gaseous Effluent Radiation Monitors Previously described in Section 8.4.1.

- END -

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3 1_75 of 133 ATTACHMENT A Page 1 of 2 GASEOUS SOURCE TERM TABLE 2.1-1a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

NUCLIDE(2)

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 RX CONTAINMENT/

SLCRS VENT Long Term, And CONTAINMENT BUILDING"'

Short Term 2.2E-02 1.5E-01 6.IE+01 5.4E-02 2.4E-01 4.7E-04 7.4E-01 8.9E-0 I 8.9E+0 I 4.5E-03 7.OE-01 1.OE-03 1.5E-02 2.5E+I01 AUXILIARY BUILDING VENT AUXILIARY BUILDING VENTILATION Long Term 4.2E-0 1 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-0 1 3.6E+01 3.2E-01 4.5E+00 2.1E-01 1.IE+00 0.0 MAIN CONDENSER/

AIR EJECTOR Long Term 2.7E-01 1.2E+00 1.6E+00 8.2E-01 2.4E+00 7.7E-02 8.OE-02 5.6E-0 I 2.3E+0 1 2.OE-01 2.8E+00 1.3E-01 6.6E-0 I 0.0 CONTAINMENT VACUUM PUpPS(3 )

Long Term 5.2E-03 5.5E-02 1.OE+01 1.LE-02 7.OE-02 4.3E-05 I.8E-01 3.1E-01 2.7E+01 6.2E-04 2.7E-0 1 8.8E-05 1.7E-03 0.0 GASEOUS WASTE SYSTEM Short Term 0.0 7.3E-02 2.3E+02 0.0 0.0 0.0 1.3E+00 0.0 2.3E+01 0.0 0.0 0.0 0.0 0.0 GASEOUS WAqSTE/PROCESS VENT (1) Containment can be purged via VV-1 (Auxiliary Building Vent),

Vent), or PV-1/2 (Gaseous Waste/Process Vent)

(2) Source Term from BVPS-2 UFSAR Table 11.3.1(312)

CV-I (Rx Containment/SLCRS (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 1R15. This change in Source Term is documented in Condition Report CR03-04830 and Calculation No. ERS-HHM 014. (3 1.1.5) (3.1.1.8) (3.1.3.10)

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1_3 1_76 of 133 ATTACHMENT A Page 2 of 2 GASEOUS SOURCE TERM TABLE 2.1-1b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

SLCRS UNFILTERED PATHWAY Long Term, And SLCRS FILTERED PATHWAY NUCLIDE(2 CONTAINMENT BUILDING(')

Short Term 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 A r-41 4.OE-05 1.4E-02 6.1E+01 5.3E-06 4.IE-03 0.0 7.2E-0 1 7.6E-0 1 8.4E+0 1 0.0 2.4E-0 1 0.0 0.0 2.5E+01 AUXILIARY BUILDING VENTILATION Long Term 4.2E-0 1 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-01 3.6E+0I 3.2E-0 I 4.5E+00 2.1E-01 I.IE+00 0.0 TURBINE BUILDING VENT TURBINE BUILDING VENTILATION Long Term 3.9E-05 1.7E-04 2.3E-04 1.IE-04 3:5E-04 1.lE-05 1.2E-05 8.1E-05 3.4E-03 2.9E-05 4.2E-04

2. 1 E-05 9.7E-05 0.0 GASEOUS WASTE/PROCESS VENT MAIN CONDENSER/

AIR EJECTOR Long Term 2.7E-01 1.2E+00 1.6E+00 8.2E-0 1 2.4E+00 7.7E-02 8.OE-02 5.6E-01 2.3E+01 2.OE-01 2.8E+00 1.3E-01 6.6E-01 0.0 Long Term Short Term CONTAINMENT VACUUM PUMPS(,)

GASEOUS WASTE SYSTEM 3.7E-04 3.9E-03 7.2E-0 1 7.8E-04 5.OE-03 3.1E-06 1.3E-02 2.2E-02 1.9E-00 4.4E-05 1.9E-02 6.3E-06 1.2E-04 0_0 0.0 1.2E-02 2.3E+02 0.0 0.0 0.0 8.3E-01 0.0 8.2E+00 0.0 0.0 0.0 0.0 0.0 Containment can be purged via VV-2 (SLCRS Unfiltered Pathway),

Pathway), or PV-1/2 (Gaseous Waste/Process Vent)

(2) Source Term from BVPS-2 UFSAR Table 11.3.2(312.3)

(3) Source Term from Calculation No. UR(B)-262(3-2.)

CV-2 (SLCRS Filtered

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 77 of 133 ATTACHMENT B Page 1 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2a BV-I MONITOR DETECTOR EFFICIENCIES (cpm/uCi/cc)

GASEOUS WASTE/

PROCESS VENT NUCLIDE AT lJTITJARY RTJT ITDTNG VENT Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135rn Xe-135 Xe-137 Xe-138 Ar-41 PRIMARY MONITOR(')

RM-VS-IO1B 9.80 E7 3.88 E5 7.38 E7 1.14 E8 1.39 E8 1.34 E8 2.25 E6 1.26 E7 1.01 E7 7.15 E7 1.12 E8 3.16 E7 1.15 E8 7.17 E7 ALTERNATE MONITOR(2)

RM-VS-109 Channel 5 2.39 E7 2.47 E7 2.95 E7 2.11 E7 2.93 E7 3.05 E7 1.56 E7 1.94 E7 1.24 E7 5.70 E6 2.91 E7 2.96 E7 2.66 E7 3.00 E7 PRIMARY MONITOR(')

RM-GW-108B 9.00 E7 3.56 E5 6.78 E7 1.05 E8 1.28 E8 1.23 E8 2.07 E6 1.16 E7 9.24 E6 6.58 E7 1.03 E8 2.91 E7 1.06 E8 6.59 E7 ALTERNATE MONITOR(2 )

RM-GW-109 Channel 5 2.43 E7 2.51 E7 3.00 E7 2.14 E7 2.98 E7 3.10 E7 1.59 E7 1.97 E7 1.26 E7 5.80 E6 2.96 E7 3.01 E7 2.70 E7 3.05 E7 RM-VS-107B 5.16 E7 5.04 E7 9.60 E7 5.16 E7 9.59 E7 9.87 E7 2.94 E7 4.17 E7 2.28 E7 1.51 E7 6.42 E7 1.05 E8 7.35 E7 7.19 E7 RM-VS-1 10 Channel 5 2.57 E7 2.67 E7 3.19 E7 2.28 E7 3.16 E7 3.29 E7 1.68 E7 2.09 E7 1.33 E7 6.15 E6 3.14 E7 3.19E7 2.87 E7 3.23 E7 Rx CONTAINMENT/

SLCRS VENT PRIMARY ALTERNATE MONITOR(')

MONITOR"2 )

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

(2) The alternate monitors (Eberline SPING Channel 5) efficiencies are corrected for detector unique installation factors. (Pressure corrections are not required for the SPING Monitors.) See Calculation Package ERS-SFL-85-031 for additional information.(3 1 1.4)

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 78 of 133 ATTACHMENT B Page 2 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2b BV-2 MONITOR DETECTOR EFFICIENCIES (cpm/uCi/cc)

NUCLIDE(')

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 SLCRS UNFILTERED PATHWAY 2HVS-RQ10I1B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 SLCRS FILTERED PATHWAY 2HVS-RQ 109B 5.83E7 7.19E7 8.85E7 6.80E7 8.73E7 8.80E7 4.6 1E4 6.06E4 2.94E7 1.55E4 7.48E7 9.07E7 7.74E7 7,90E7 WASTE GAS STORAGE VAULT VENT 2RMQ-RQ303B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 I.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 DECON BUILDING VENT 2RMQ-RQ301B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 CONDENSATE POLISHING BUILDING VENT 2HVL-RQI 12B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 Efficiencies from Calculation Package ERS-SFL-86-026. 312 1 )

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 79 of 133 ATTACHMENT C Page 1 of I MODES OF GASEOUS RELEASE Table 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT RP 1; VV-1, Auxiliary Building VentO 1 )

RP 2; CV-1, Rx Containment/SLCRS Vent01 )

RP 3; PV-l/2, Gaseous Waste/Process Vent(2)

RP 4; VV-2 SLCRS Unfiltered Pathway(1)

RP 5; CV-2, SLCRS Filtered Pathway Vent(l)

RP 6; CB-2, Condensate Polishing Bldg Vent01 )

RP 7; WV-2, Waste Gas Storage Vault Vent0')

RP 8; DV-2, Decontamination Bldg Vent(1 )

RP 9; TV-2, Turbine Bldg Vent(1)

RELEASE MODE 1 Aux. Bldg.

Ventilation Leakage Collection Exhaust Main Cond. Air Ejector, Waste Gas, Containment Vacuum Contiguous Areas RELEASE MODE 2 Containment Purge(3)

Same As Mode I Same As Mode I Containment Purge(3)

Same As Mode 1 (4)

RELEASE MODE 3 Same As Mode I Same As Mode I and Containment Purge(3)

Same As Mode I Same As Mode I Same As Mode I and Containment Purge(3)

(4)

RELEASE MODE 4 Same As Mode 1 Same As Mode I Same As Mode I and Containment Purge Same As Mode 1 Same As Mode 1 (4)

Aux. Bldg.

Ventilation (4)

(4)

NOTE: For the purpose of implementing 10 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 1 (4) Not normally a radioactive release point

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

80 of 133 ATTACHMENT D Page 1 of 2 RADIONUCLIDE MIX TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

RX CONTAINMENT/

SLCRS VENT AUXILIARY BUILDING VENT GASEOUS WASTE/PROCESS VENT Long Term, And NUCLIDE12 CONTAINMENT BUILDING")

AUXILIARY BUILDING VENTILATION MAIN CONDENSER/

AIR EJECTOR CONTAINMENT VACUUMM pUMpS(3)

GASEOUS WASTE SYSTEM 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.

1-131 1-132 1-133 1-134 1-135 Co-58 Co-60 Mn-54 Fe-59 Sr-89 Sr-90 Cs-134 Cs-137 C-14 Ar-41 Short Term 2.2E-02 1.5E-01 6.]E+01 5.4E-02 2.4E-0 1 4.7E-04 7.4E-01 8.9E-0 I 8.9E+01 4.5E-03 7.OE-01 1.0E-03 1.5E-02 1.2E-03 0.0 2.OE-04 0.0 0.0 7.5E-04 3.4E-04 2.2E-04 7.5E-05 I.7E-05 3.OE-06 2.2E-04 3.8E-04 I.OE+00 2.5E+0 I Long Term 4.2E-0 I 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-01 3.6E+01 3.2E-01 4.5E+00 2.IE-01 1.1E+00 4.6E-02 0.0 6.7E-02 0.0 0.0 6.OE-02 2.7E-02 1.8E-02 6.OE-03 1.3E-03 2.OE-04 1.8E-02 3.0E-02 0.0 0.0 Long Term 2.7E-0 I 1.2E+00 1.6E+00 8.2E-0 I 2.4E+00 7.7E-02 8.OE-02 5.6E-01 2.3E+01 2.OE-0 I 2.8E+00 1.3E-01 6.6E-01 2.1E-02 0.0 3.OE-02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Long Term 5.2E-03 5.5E-02 1.0E+01 1.1E-02 7.OE-02 4.3E-05 1.8E-01 3.1E-01 2.7E+01 6.2E-04 2.7E-0 I 8.8E-05 1.7E-03 6.6E-03 3.5E-05 1.2E-03 6.6E-06 2.OE-04 2.2E-04 1.OE-04 6.9E-05 2.2E-05 5.2E-06 9.2E-07 6.9E-05 1.2E-04 0.0 0.0 Short Term 0.0 1.2E-02 2.3E+02 0.0 0.0 0.0 8.3E-01 0.0 8.2E+00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7.OE+00 0.0 (1) Containment can be purged via VV-1 (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)

(2) Source Term from BVPS-2UFSAR Table 11.3-1(3112)

(3) See Note (3) from ATTACHMENT A Table 2. 1-la (3.l.5)1.1.8)(3.1.3.10)

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 81 of 133 ATTACHMENT D Page 2 of 2 RADIONUCLIDE MIX TABLE 2.2-2b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)

SLCRS UNFILTERED PATHWAY Long Term, And NUCLIDE(2 CONTAINMENT BUILDING(')

Short Term 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 1-131 1-132 1-133 1-134 1-135 Co-58 Co-60 Mn-54 Fe-59 Sr-89 Sr-90 Cs-134 Cs-137 C-14 Ar-41 4.OE-05 1.4E-02 6.]E+01 5.3E-06 4.1E-03 0.0 7.2E-0 I 7.6E-01 8.4E+01 0.0 2.4E-01 0.0 0.0 2.7E-05 0.0 2.6E-06 0.0 0.0 7.5E-02 3.4E-02 2.2E-02 7.5E-03 1.7E-03 3.OE-04 2.2E-02 3.8E-02 1.OE+00 2.5E+01 SLCRS FILTERED PATHWAY AUXILIARY BUILDING VENTILATION Long Term 4.2E-0 1 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-01 3.6E+01 3.2E-01 4.5E+00 2.1E-01 1.1 E+00 4.6E-03 0.0 6.7E-03 0.0 0.0 6.OE-04 2.7E-04 1.8E-04 6.OE-05 1.3E-05 2.OE-06 1.8E-04 3.OE-04 0.0 0.0 TURBINE BUILDING VENT TURBINE BUILDING VENTILATION Long Term 3.9E-05 1.7E-04 2.3E-04 1.1E-04 3.5E-04 1.1E-05 1.2E-05 8.1E-05 3.4E-03 2.9E-05 4.2E-04 2.1E-05 9.7E-05 6.5E-04 0.0 8.7E-04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MAIN CONDENSER/

AIR EJECTOR Long Term 2.7E-01 1.2E+00 1.6E+00 8.2E-0 1 2.4E+00 7.7E-02 8.OE-02 5.6E-01 2.3E+01 2.OE-0I 2.8E+00 1.3E-01 6.6E-01 2.1E-02 0.0 3.OE-02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GASEOUS WASTE/PROCESS VENT CONTAINMENT VACUUM PUMPS(31 Long Term 3.7E-04 3.9E-03 7.2E-0 I 7.8E-04 5.OE-03 3.]E-06 1.3E-02 2.2E-02 1.9E-00 4.4E-05 1.9E-02 6.3E-06 1.2E-04 4.7E-04 2.5E-06 8.4E-05 4.7E-07 1.4E-05 1.6E-05 7.4E-06 4.9E-06 1.6E-06 3.7E-07 6.6E-08 4.9E-06 8.4E-06 0.0 0.0 GASEOUS WASTE SYSTEM Short Term 0.0 1.2E-02 2.3E+02 0.0 0.0 0.0 8.3E-01 0.0 8.2E+00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7.OE+00 0.0 (1) 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 11.3-2.3113)

(3) See Section 8.1.1.1

1 TABLE 2.2-3 DISTANCES OF LIMITING MAXIMUM INDIVIDUAL RECEPTORS TO RELEASE POINTS FOR ANNUAL X/Q VALUES (meters)

Cd VEGETABLE M

SITE BOUNDARY*

GARDEN MILK COW MILK GOAT MEAT ANIMAL RESIDENT 0

DOWNWINDC SECTOR GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV M

(1)

(2)

N 670 579 413 2,623 2,423 4,651 4,418 4,152 3,919 2,527 2,295 NNE 535 792 632 2,740 2,461 6,276 6,033 2,848 2,605 2,639 2,461 Z

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

CA)

ENE 490 448 394 1,674 1,658 6,824 6,671 708 1,562 7

z E

545 546 551 1,979 1,922 7,065 6,998 4,265 4,200 4,265 4,200 756 1,922 ESE 575 607 672 1,577 1,619 2,865 2,899 1,577 1,619 1,577 1,650 Cn SE 575 701 815 1,835 1,961 5,729 5,848 5,729 5,848 3,299 3,420 1,835 1,961 H '

SSE 655 762 912 1,738 1,933 5,053 5,244 9,977 10,166 1,770 1,964 1,432 1,628 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 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

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

c 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

Distances for ground releases are measured from the center point between the BV-1 and BV-2 Containment Buildings. Distances for elevated release are measured from the BV-I Cooling Tower. Elevated release is applicable to PV-1/2. Ground release is applicable to C, -

C all other release points.

x 9 (1) TV-2 and CB-2 (2) VV-1, CV-1, VV-2, CV-2, DV-2, WV-2

TABLE 2.2-4 CV-I AND CV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3

(]E-7 sec/m )

INDIVIDUAL RECEPTORS DOWN-SITE VEGE-WIND BOUND-TABLE MILK MILK MEAT RESI-0-

SECTOR ARY GARDEN COW GOAT ANIMAL DENCE 0.5 DISTANCES TO THE CONTROL LOCATION, IN MILES 0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 125.0 50.2 102.0 85.8 54.5 31.1 27.8 24.1 27.5 23.8 22.3 163.0 278.0 487.0 924.0 302.0 12.80 5.360 6.27 13.50 233.0 39.5 18.70 11.80 7.68 5.82 4.240 3.480 2.660 2.280 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 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 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 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 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 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 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 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 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 13.90 9.050 12.30 13.90 160.0 29.2 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 19.30 5.720 17.70 19.30 283.0 49.8 23.50 14.60 10.30 7.72 5.690 4.650 3.620 3.090 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 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 12.200 194.00 8.660 40.50 200.00 1710.0 262.0 123.00 79.80 55.00 42.30 34.000 28.200 19.400 16.700 63.00 1.720 15.40 92.30 547.0 86.4 40.80 26.20 17.60 13.50 10.100 8.350 6.560 5.660 tlp IT1 Hn 0

C)

-ri 0

c-n z

uTJ 00 J0~

w*

W.

0 0

ýi FF CD CD C"D.

co 0

C, 0

CD z

t D

C-.

Y TABLE 2.2-5 VV-1 AND VV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3

(I1E-7 sec/m)

INDIVIDUAL RECEPTORS DOWN-SITE VEGE-WIND BOUND-TABLE MILK MILK MEAT RESI-0-

SECTOR ARY GARDEN COW GOAT ANIMAL DENCE 0.5 DISTANCES TO THE CONTROL LOCATION, IN MILES 0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 0

C-)

0 ti-I 0

r-#)

ti-i

~T1 ti-iz H

ci~

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 152.0 62.3 132.0 110.0 67.8 38.0 33.3 29.1 15.00 5.980 7.06 7.66 2.150 7.08 57.90 1.240 0.269 1.24 13.60 1.270 6.66 0.828 1.990 1.99 7.64 3.200 7.64 7.27 1.030 1.030 2.88 7.41 1.080 0.382 7.19 15.90 276.0 7.95 189.0 60.20 156.0 50.40 135.0 38.80 116.0 7.64 76.7 7.27 86.2 10.10 87.0 6.38 127.0 22.90 140.0 15.70 204.0 22.40 347.0 18.00 715.0 48.60 1410.0 271.00 1820.0 121.00 601.0 49.9 22.70 13.70 8.75 6.52 4.69 3.810 2.900 2.470 32.0 12.20 7.31 4.99 3.69 2.87 2.320 1.920 1.630 24.8 12.70 7.51 5.09 3.73 2.47 1.980 1.500 1.270 20.6 10.20 6.01 4.31 3.14 2.41 1.930 1.290 1.080 17.7 6.57 3.86 2.61 1.90 1.34 1.070 0.883 0.774 11.9 5.59 3.29 2.05 1.49 1.05 0.842 0.630 0.531 13.5 6.37 3.75 2.53 1.84 1.20 0.960 0.790 0.666 13.7 5.98 3.53 2.02 1.48 1.04 0.833 0.688 0.531 20.3 7.56 4.48 3.04 2.23 1.57 1.260 1.050 0.885 23.6 8.87 5.28 3.60 2.66 2.07 1.670 1.260 1.070 34.8 18.40 11.40 6.38 4.71 3.66 2.960 2.230 1.900 61.3 27.70 16.60 11.40 8.49 6.19 5.020 3.880 3.300 132.0 60.30 36.50 17.70 13.20 10.40 8.440 7.060 6.040 269.0 120.00 73.00 48.50 36.40 28.70 23.400 15.900 13.600 350.0 164.00 100.00 66.60 50.10 39.50 32.300 21.900 18.800 114.0 52.80 32.20 21.00 15.80 11.60 9.460 7.360 6.310 0

ti-i ti-i (D

CD 0-t 32.8 3.65 3.300 6.10 28.7 7.08 4.040 1.850 7.08 26.2 15.70 9.980 13.80 201.0 22.40 6.230 20.40 345.0 18.00 10.600 --

14.70 598.0 48.60 35.000 1.920 48.60 1030.0 262.00 9.520 47.80 345.0 83.40 1.840 18.10 uJ~

z 0

0~

CD C-CD 0

Y 1-TABLE 2.2-6 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 (IE-7 sec/mr)

INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES DOWN-SITE VEGE-WIND BOUND-TABLE MILK MILK MEAT RESI-0-

SECTOR ARY GARDEN COW GOAT ANIMAL DENCE 0.5 0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5-1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0.0082 0.0280 0.0110 0.0110 0.0360 0.0420 0.0750 0.2060 5.740 7.640 6.500 0.126 0.029 0.033 0.007 0.008 6.720 1.910 2.27 6.690 1.430 6.14

.074 1.610 0.350 1.61 9.090 1.770 8.300 1.240 2.870 2.87 11.600 4.570 11.60 7.890 1.230 1.230 3.05 7.390 1.160 0.357 7.20 3.760 3.490 6.06 3.610 2.140 0.872 3.61 3.900 2.560 3.47 4.350 1.420 3.98 2.490 0.764 2.02 2.530 1.780 0.163 2.53 0.074 0.305 1.67 6.460 0.224 1.81 6.790 0.0289 23.1000 8.2700 5.32 2.56 1.91 1.480 1.200 0.996 0.846 6.890 0.0175 14.5000 6.9800 5.47 3.27 2.69 1.770 1.430 1.290 1.100 0.055 0.0069 0.1160

.2300 7.10 5.38 3.68 2.880 2.090 1.880 1.570 0.525 0.0135 0.3310 7.2800 6.02 4.75 3.22 2.620 2.030 1.710 1.100 8.300 0.0124 17.1000 7.8600 6.20 3.67 2.83 2.190 1.730 1.280 1.200 11.200 0.0208 12.7000 8.1400 4.78 3.00 2.20 1.360 1.160 0.830 0.737 7.890 0.4770 7.4000 7.5700 4.45 2.79 2.05 1.460 1.180 0.811 0.686 9.770 0.3030 9.4400 6.9300 4.06 2.58 1.89 1.170 0.937 0.646 0.546 6.310 0.7960 8.5100 8.4900 4.98 3.37 2.47 1.380 1.110 0.774 0.655 5.820 26.1000 9.1000 4.0300 3.11 2.11 1.56 1.030 0.834 0.807 0.684 3.900 36.1000 15.9000 4.9300 3.12 1.77 1.57 1.201 1.060 1.150 0.977 4.350 0.3870 17.8000 4.9000 3.53 2.36 1.64 1.460 1.210 0.920 0.781 2.490 0.0147 8.7200 6.2300 3.68 2.50 1.84 0.741 1.120 0.851 0.795 2.530 0.0202 0.0549 0.0809 3.07 2.50 1.84 1.110 0.686 0.791 0.731 0.073 0.0084 0.0650 0.1170 3.66 2.30 1.69 1.210 0.903 0.804 0.683 6.590 0.0135 6.7800 5.0200 2.96 1.93 1.49 1.050 0.849 0.705 0.599 00 t-,1 PCI Cn 0

C-)

C)

CA trl0 CA tTl z

H CA t.CJ Cd'

~Cd C,z

~

C-

-h

,-q WD CD CD

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

C-CD CD 0CD

TABLE 2.2-7 TV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3

(1E-7 sec/m)

INDIVIDUAL RECEPTORS DISTANCES TO THE CONTROL LOCATION, IN MILES DOWN-SITE VEGE-WIND BOUND-TABLE MILK MILK MEAT RESI-0-

SECTOR ARY GARDEN COW GOAT ANIMAL DENCE 0.5 0.5-1.0-1.5-2.0-2.5-1.0 1.5 2.0 2.5 3.0 3.0-3.5-4.0-4.5-3.5 4.0 4.5 5.0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 105.0 102.0 96.6 84.1 60.7 37.1 41.8 34.0 32.7 29.7 24.1 159.0 264.0 404.0 735.0 247.0 14.00 7.37 51.90 13.20 6.49 7.25 7.06 7.16 3.64 6.73 14.80 20.80 16.90 44.50 216.00 71.00 5.740 6.74 2.130 6.83 1.230 0.268 1.23 1.280

.829 1.980 1.98 3.100 7.25 1.020 1.020 2.85 1.070 0.384 6.96 3.310 6.00 3.890 1.800 6.73 9.550 13.10 6.010 19.10 10.100 13.90 32.500 1.870 44.50 9.100 43.90 1.820 17.00 14.80 244.0 7.64 161.0 53.80 132.0 46.30 115.0 35.70 99.2 7.25 65.8 7.06 73.5 9.69 74.2 6.27 109.0 20.90 120.0 14.80 174.0 20.80 301.0 16.90 636.0 44.50 1310.0 222.00 1720.0 99.40 557.0 42.6 20.50 12.70 8.18 6.15 28.8 11.40 6.94 4.79 3.56 23.0 12.10 7.24 4.95 3.64 19.4 9.89 5.85 4.23 3.09 16.6 6.32 3.75 2.55 1.87 11.1 5.36 3.19 2.00 1.46 12.6 6.12 3.64 2.47 1.81 12.7 5.71 3.41 1.97 1.45 18.6 7.13 4.29 2.94 2.17 21.3 8.31 5.03 3.46 2.57 31.2 17.20 10.40 6.10 4.54 53.6 25.30 15.60 10.80 8.09 111.0 53.90 33.50 16.50 12.40 218.0 104.00 65.40 44.20 33.60 279.0 140.00 88.80 60.30 45.90 924.0 45.90 28.90 19.20 14.60 4.45 2.78 2.42 2.38 1.32 1.03 1.18 1.02 1.53 2.00 3.54 5.93 3.640 2.770 2.380 2.250 1.870 1.590 1.950 1.480 1.250 1.900 1.270 1.070 1.060 0.871 0.735 0.829 0.621 0.524 0.945 0.779 0.658 0.818 0.676 0.572 1.230 1.020 0.866 1.620 1.230 1.040 2.870 2.170 1.850 4.830 3.750 3.200 0

>r r-)

0 CJ) 0 z

H C,

C C,

Co -~

~ C C,

C, C,

0 C,

ctz

(-4 CD 0'

0D 9.82 8.040 6.760 5.790 26.70 22.000 15.000 12.900 36.60 30.100 20.600 17.700 10.80 8.880 6.950 5.980

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

87 of 133 ATTACHMENT F Page5 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-8 DV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (1E-7 sec/mr3)

Same as Table 2.2-4

I JProcedure Number:

Beaver Valley Power Station Proedre umer

______________________________________________j1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

88 of 133 ATTACHMENT F Page 6 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-9 WV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (1E-7 sec/mr3)

Same as Table 2.2-4

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

89 of 133 ATTACHMENT F Page 7 of 7 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 ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS Same as Table 2.2-7 I

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1_3 1_90 of 133 ATTACHMENT G Page 1 of 2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS NUCLIDE(1 )

Ki TOTAL BODY DOSE FACTOR mrem/yr Per uCi/m 3

Li SKIN DOSE FACTOR mrem/yr Per uCi/m 3

Mi GAMMA AIR DOSE FACTOR mrad/yr Per uCi/m 3

Ni BETA AIR DOSE FACTOR mrad/yr Per uCi/m 3

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02 2.94E+02 3.12E+03 1.811E+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.5 1EE+03 9.21 E+03 9.30E+03 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 (1) The listed dose factors are for radionuclides that may be detected in gaseous effluents.

Beaver Valley Power Station Procedure Num:

0 2

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

91 of3133 ATTACHMENT G Page 2 of 2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES Vi0l)

Bi (1),(2)

Mi(3)

Bi(3)

TOTAL BODY GAMMA AIR TOTAL BODY GAMMA AIR NUCLIDE(4)

DOSE FACTOR DOSE FACTOR DOSE FACTOR DOSE FACTOR mrem/yr mrad/yr mrem/yr mrad/yr Per Per Per Per uCi/sec uCi/sec uCi/sec uCi/sec Kr-83m 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 3.19E-10 7.81E-5 1.55E-6 5.13E-4 1.39E-3 7.99E-4 1.64E-5 1.38E-5 1.05E-5 2.4 1E-4 1.41E-4 6.OOE-5 8.11 E-4 1.02E-3 1.75E-8 1.16E-4 2.35E-6 7.74E-4 2.09E-3 1.20E-3 2.47E-5 2.11E-5 1.56E-4 3.66E-4 2.12E-4 9.05E-5 1.22E-3 1.53E-3 4.58E-8 4.70E-4 5.54E-6 1.45E-3 4.09E-3 1.25E-3 1.67E-4 1.32E-4 1.54E-4 6.2 1E-4 6.96E-4 9.66E-5 2.22E-3 2.68E-3 3.96E-5 7.06E-4 8.40E-6 2.19E-3 6.16E-3 1.88E-3 3.09E-4 2.61E-4 2.76E-4 9.50E-4 1.05E-3 1.46E-4 3.34E-3 4.02E-3 (1) Vi and B values used to implement Modes 1, 2, and 3 of Section 2.2.1 (10CFR2O)

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

(3) Vi and Bi values to implement Mode 4 of Section 2.2.1 (10CFR20) and to implement monitor setpoint determinations of Section 2.1.2 and 2.1.4 (4) The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

BPProcedure Number:

yPower Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 92 of 133 ATTACHMENT H Page 1 of 1 ORGAN DOSE PARAMETERS ORGAN DOSE PARAMETERS Table 2.2-13 PiT VALUES FOR A CHILDFOR THE BEAVER VALLEY SITE (mrem/yr per uCi/cu meter) 2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 N ucl id e H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 C o-58 Co-60 Zn-65 Se-75 Rb-86 S r-8 9 Sr-90 Y -91 Zr-95 Nb-95 N b-9 7 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-I 25 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-1 40 La-140 Ce-I141 Ce-144 Bone 0.OOE+00 2.60E+06 0.0OE+00 0.0 OE +00 2.0 7E +04 0.OOE+00 0.00E1+00 0.00E+00 4.25E+04 2.05E+04 o.00E+00 5.9 9E +05 1.0 I E+08 9.14E+05 1.90E+05 2.3 5E +04 4.2 9E-01 0.0CE+00 1.78E-03 2.79E+03 1.36E+05 1.69E+04 5.74E+04 9.84E+04 2.49E+04 1.92E+04 4.8 1E+04 1.66E+04 6.5 1E+05 6.5 IE+04 9.07E+05 7.4 OE + 04 6.44E+02 3.92E+04 6.7 7E+06 Liver

1. 12E+03

1. 14E+05 0.0OE+00 4.29E+04 3.34E+04 9.03E+02

). 77E+03 1.31 E+04

1. 13E+05 1.50E+04 1.98E+05 O.OOE+00 C.COE+00 0.00E+00 4.18E+04

9. 18E+03

7. 70E-02

1. 72 E+02 3.48 E-0 3 0.001E+00

0. 00E+00 I. 14 E+04 7.40E+02 7.59E+02 8.55E+03 6.85 E+03 4.81 E+04 2.03E+04 1.01 E+06 I. 71 E+05 8.25E+05 6.48E+01 2.25 E+02 1.95 E+04

2. 12 E+06 T. Body 1.12E+03 9.8 8E+04 I.54E+02 9.5 1E+03 1.67E+04 1.07E+03 3.1 6E+03 2.26E+04 7.03E+04 3.14E+04 1.1 4E+05 1.72E+04 6.44E+06 2.44E+04 3.70E+04 6.55E+03 3.60E-02 4.26E+01 5.77E-02 1.0 7E+03 1.69E+04 9.14E+03 2.C0E+04 2.0 7E+04 3.02E+03 3.04E+03 2.7 3E+04 7.70E+03 2.2 5E+05 1.1 6E+05 1.28E+05 4.3 3E+03 7.5 5E+01 2.90E+03 3.6 1E+05 Thyroid

1. 12E+03 0.001E+00 8.55E+0I 0.00E+00 0.00E+00 0.001E+00

0. 00E+00 0.001E+00 0.00E+00

1. 15E+04 0.00E+00 0.0OE+03 0.001E+00 0.00E+00 0.001E+00 0.00E+00 0.001E+00

0. OOE+00 0.00E+00 0.00E+00 0.001E+00 0.00E+00 1.26E+02 9.10E+01 6.07E+03 6.33 E+03 I. 62 E+07 3.85 E+06 0.00E+00 O.OOE+0C

0. 00 E+ 00

0. 00 E+ 0C

0. 00 E+0C

0. 00 E+00

0. 00 E+ 00 Kid ney 1.1 2E+03 0.0CE+00 2.43E+01 1.00E+04 0.0OE+00 0.0CE+00 0.00E+00 C.0OE+00 7.14E+04 1.97E+04 0.OOE+00 0.00E +00 0.OOE+00 0.00E +00 5.96E+04 8.62E+03 8.55E-02 3.92E+02 5.07E1-02 7.03E+03 1.84E+05 2.12E+04 0.0OE+00 0.00E+00 6.36E+04 5.03E+04 7.8 8E+04 3.3 8E+04 3.3 OE +05 9.5 5E +04 2.82E+05 2.1 IE+01 0.0CE+00 8.5 5E +03 1.1 7E+06 Lung 1.12E+03 0.00E+00 1.701E+04 1.58 E+06 1.27E+06 5.07E+05 1.1 1E+06 7.07E+06 9.95E+05 7.45E+04 0.00E+00 2.16E+06 1.48E+07 2.63 E+06 2.23 E+06 6.14E+05 3.42 E+0 3 1.3 5E+05 9.51 E+02 6.62E+05 1.43E+07 5.48E+06 3.24E+06 2.32E+06 1.48 E+0 6 1.76E+06 0.00E+00 0.00E+00 1.21 E+05 1.4 5E+04 1.04E+05 1.74E+06 1.83E+05 5.44E+05 1.20E+07 GI-LLI 1.12E+03 4.22 E+04 1.08E+03 2.29E+04 7.07E+04 1.32E+04 3.44E+04 9.62E+04 I.63E+04 1.58E+04 7.99E+03 1.67E+05 3.43 E+05 1.84E+05 6.11 E+04 3.70E+04 2.78 E-+04 1.27E+05 4.81 E+03 4.48E+04 4.29E+05 1.00E+05 1.64E+05 4.03E+04 7.14E+04 1.82E+05 2.84 E+03 5.48E+03 3.85E+03 4.18E+03 3.62 E+03 1.02E+05 2.26E+05 5.66 E+04 3.89E+05 Calculated per ODCM equation 2.2-13

1Procedure Number:

Beaver Valley Power Station I

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 93 of 133 ATTACHMENT I Page 1 of 1 MODES OF GASEOUS RELEASE TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT RP 1; VV-1, Auxiliary Building Vent(l)

RP 2; CV-1, Rx Containment/SLCRS Vent(M RP 3; PV-1/2, Gaseous Waste/Process Vent(2)

RP 4; VV-2 SLCRS Unfiltered Pathway(l)

RP 5; CV-2, SLCRS Filtered Pathway(l)

RP 6; CB-2, Condensate Polishing Bldg Vent(l)

RP 7; WV-2, Waste Gas Storage Vault VentO 1 )

RP 8; DV-2, Decontamination Bldg Vent(')

RP 9; TV-2, Turbine Bldg Vent(1)

RELEASE MODE I Aux. Bldg.

Ventilation Leakage Collection Exhaust Main Cond. Air Ejector, Waste Gas, Containment Vacuum Contiguous Areas RELEASE MODE 2 Containment Purge(3)

Same As Mode I Same As Mode I Containment Purge(3)

Same As Mode 1 RELEASE MODE 3 Same As Mode I Same As Mode 1 and Containment Purge(3)

Same As Mode I Same As Mode I Same As Mode 1 and Containment Purge(3)

(4)

RELEASE MODE 4 Same As Mode 1 Same As Mode I Same As Mode I and Containment Purge Same As Mode I Same As Mode 1 (4)

Aux. Bldg.

Ventilation (4)

(4)

NOTE: For the purpose of implementing 10 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 1 (4) Not normally a radioactive release point

Beaver Valley Power Station Procedure umber:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 94 of 133 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= Adult Nuclide I H-3 2

P -32 3

Cr-51 4

Mn-54 5

Fe-59 6

Co-57 7

Co-58 8

Co-60 9

Zn-65 10 Se-75 II Rb-86 12 Sr-89 13 Sr-90 14 Y-91 15 Zr-95 16 Nb-95 17 Nb-97 18 Mo-99 19 Tc-99m 20 Ru-103 21 Ru-106 22 Ag-110m 23 Sb-124 24 Sb-125 25 Te-127m 26 Te-129m 27 1-131 28 1-133 29 Cs-134 30 Cs-136 31 Cs-137 32 Ba-140 33 La-140 34 Ce-141 35 Ce-144 Bone 0.00 E+00 1.32E+06 0.00 E+00 0.00E+00

1. 181E +04 0.00E+00 0.00E+00 0.00E+00 Li ver 1.26E+03 7.7 1E+04 0.00E+00 3.96E+04 2.78E+04 6.92E+02 1.5 8E+03 1.15E +04 T. Body 1.261E+03 5.01 E+ 04 1.001E+02 6.30 E+ 03 1.06E+04 6.71 E+ 02 2.07 E+ 03 1.48 E+ 04 Thyroid 1.26E1+03 0.00E+00 5.9 5E +0 1 0.00E+00 0.0013+00 O.00E+00 0.OOE+00 0.0OE+00 K idney 1.26E+03 0.00E+00 2.28E+01 9.841E+03 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Lung 1.26E+03 0.00E+00 1.44E+04 1.40E+06 1.02E+06 3.70E +05 9.28E+05 5.97E+06 GI-LLI 1.26 E+03 8.64E+04 3.321E+03 7.7413+04 1.881E+05 3.14E+04 1.06E+05 2.85E+05 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 4.44E+04 3.24E+04 6.78 E+04 2.48E+04 4.26E+04 1.6 1E+05 3.42E+04 0.00E+00 3.04E+05 9.92E+07 4.62E+05 1.07 E +05 1.41 E+04 2.22E-01 0.OOE+00 1.0313-03 1.53 E +03 6.91 E+04 1.08 E +04 3.12 E +04 5.34E+04 1.261E+04 9.76 E +03 2.52 E1+04 8.64E+03 3.73 E +05 3.90E+04 4.78E+05 3.90E+04 3.44E+02 1.99E+04 3.43 E+06 1.35E+05 0.00E+00 0.00E+00 0.00E+00 3.4 4E1+0 4 7.8 2E +0 3 5.62E-02 1.211E+02 2.911E-03 0.00E+00 0.00E+00 1.00E+04 5.89E+02 5.95E+02 5.77E+03 4.67E+03 3.5 8E+04 1.4 8E+04 8.48E+05 1.46E+05 6.211E+05 4.90E+0 I 1.74E+02 1.3 5E+04 1.43E+06 5.90E+ 04 8.72 E+ 03 6.10E+06 1.24 E+ 04 2,33 E+ 04 4.211E+03 2.05 E1-02 2.30E+01 3.70E-02 6.58E+02 8.72 E+ 03 5.94 E+ 03 1.241E+04 1.26 E+ 04 1.57E+03 1.58E+03 2.05 E+ 04 4.52 E+ 03 7.28 E+ 05 1.10E+05 4.28 E+ 05 2.57 E+ 03 4.58 E+ 01 1.531E+03 1.84 E+ 05 0.OOE+00 0.OOE+00 0.00E+00 0.0013+00 0.OOE+00 0.OOE+00 0.00E+00 0,OOE+00 0,00E+00 0,00E+00 0.OOE+00 0.OOE+00 7.55E+01 5.40E +01 3.2 9E+03 3.44E+03 1.19E+07 2.15E+06 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.42 E+04 7.74 E+03 6.54 E-0 2 2.91 E+02 4.24E-02 5.83E+03 1.34E+05 1.97E+04 0.00E+00 0.00E+00 4.58 E+04 3.66E+04 6.13 E+04 2.58E+04 2.87E+05 8.56E+04 2.22E+05 1.671E+01 0.00E+00 6.26E+03 8.48E+05 0.0OE+00 1.40E+06 9.60E+06 1.70E+06 1.77E+06 5.05E+05 2.40E+03 9.12E1+04 7.64E+02 5.05E+05 9.36E+06 4.63E+06 2.48E1+06 1.74E+06 9.60E+05 1.1 6E +06 O.OOE+00 0.0OE+00 9.76E+04 1.20E+04 7.52E+04 1.27E+06 1.36E1+05 3.62E1+05 7.78E+06 1.66E+04 3.50E+05 7.22E+05 3.85E+05 1o50E+05 1.04 E+0 5 2.42E+02 2.48E+05 4.16E+03 1.10E+05 9.12E+05 3.02E+05 4.06E+05 1.011E+05

1. 50E+05 3.83E+05 6.28E+03

8. 88 E+03 1.04E+04 1.171E+04 8.40E+03 2.18E+05 4.58E+05 1.20E+05 8.16E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 95-of 133 ATTACHMENT J Page 2 of 19 P&I ORGAN DOSE FACTORS Table 2.3-3 R VALUES FOR BEAVER VALLEY SITE (mrne/yr per uCilcu meter)

Pathway= Inhalation Age Group= Teen 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P-32 Cr-5 I Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-i 10m Sb-124 Sb-125 Te-127m Te-129mn 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 1.89E+06 0.00E+00 0.OOE+00 1.59E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.86E+04 4.44E+04 0.OOE+00 4.34E+05 1.08E+08 6.61 E+05 S.46E+05 1.86E+04 3.14E-01 0.OOE+00 1.38E-03 2.10E+03 9.84E+04 1.38E+04 4.30E+04 7.38E+04 1.80E+04 1.39E+04 3.54E+04 1.22E+04 5.02E+05 5.15E+04 6.70E+05 5.47E+04 4.79E+02 2.84E+04 4.89E+06 Liver 1.27E+03 1.I OE+05 0.OOE+00 5.1 IE+04 3.70E+04 9.44E+02 2.07E+03 1.5 1E+04 1.34E+05 3.24E+04 1.90E+05 0.OOE+00 0.OOE+00 0.0OE+00 4.5 8E+04 1.03E+04 7.78E-02 1.69E+02 3.86E-03 0.OOE+00 0.OOE+00 1.3 1E+04 7.94E+02 8.08E+02 8.16E+03 6.58E+03 4.9 ]E+04 2.05E+04 1.13E+06 1.94E+05 8.48E+05 6.70E+01 2.36E+02 1.90E+04 2.02E+06 T. Body 1.27 E+ 03 7.16E+ 04 1.35E+02 8.40E+03 1.43E+04 9.20E+ 02 2.78E+03 1.98E+04 6.24E+ 04 6.78E+04 8.40 E+ 04 1.25 E+ 04 6.68 E+ 06 1.77E+04 3.15 E+ 04 5.66E+ 03 2.84 E-02 3.22E+01 4.99E-02 8.96 E+ 02 1.24E+04 7.99 E+ 03 1.68E+04 1.72 E+ 04 2.18E+ 03 2.25 E+ 03 2.64E+ 04 6.22 E+ 03 5.49E+ 05 1.37E+05 3.11 E+ 05 3.52 E+ 03 6.26E+ 01 2.17 E+ 03 2.62 E+ 05 Thyroid 1.27E+03 0.OOE+00 7.50E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.48E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 9.76E+01 7.04E+0 1 4.38E+03 4.58E+03 1.46E+07 2.92E+06 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 1.27E+03 0.OOE+00 3.07 E+01 1.27E+04 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 8.64E+04 4.26E+04 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 6.74E+04 1.00E+04 9.12E-02 4.11E+02 5.76E-02 7.43 E+03 1.96E+05 2.50E+04 0.00E+00 0.OOE+00 6.54E+04 5.19E+04 8.40E+04 3.59E+04 3.75 E+05 1.10E+05 3.04E+05 2.28 E+01 0.OOE+00 8.88E+03 1.21 E+06 Lung 1.27E+03 0.OOE+00 2.1OE+04 1.98E+06 1.53E+06 5.86E+05 1.34E+06 8.72E+06 1.24E+06 1.61E+05 0.0OE+00 2.42E+06 1.65E+07 2.94E+06 2.69E+06 7.5 1E+05 3.93E+03 1.54E+05 1.15E+03 7.83E+05 1.6 IE+07 6.75E+06 3.3 4E+06 2.74E+06 1.66E+06 1.98E+06 0.OOE+00 0.OOE+00 1.46E+05 1.78E+04 1.2 1E+05 2.03E+06 2.14E+05 6.14E+05 1.34E+07 GI-LLI 1.27E+03 9.28E+04 3.OOE+03 6.68E+04 1.78E+05 3.14E+04 9.52E+04 2.59E+05 4.66E+04 3.42E+04 1.77E÷04 3.71E+05 7.65E+05 4.09E+05 1.49E+05

9. 68E+04 2.17E+03 2.69E+05 6.13E+03

1. 09E+05 9.60E+05 2.73E+05 3.98E+05 9.92E+04 1.59E+05 4.05E+05

6. 49E+03 1.03E+04 9.76E+03 1.09E+04 8.48E+03 2.29E+05 4.87E+05 1.26E+05 8.64E+05 Calculated per ODCM equation 2.3-22

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

96 of 133 ATTACHMENT J Page 3 of 19 P&I ORGAN DOSE FACTORS Table 2.3-4 R VALUES FOR BEAVER VALLEY SITE (mrn-t/yr per uCi/cu meter)

Pathway = Inhalation Age Group= Child 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nu cli de H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129mn 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.00E+00 2.60E+06 0.OOE+00 0.OOE+00 2.07E+04 0.OOE+00 0.OOE+00 0.OOE+00 4.25E+04 2.05E+04 0.00E+00 5.99E+05 1.01 E+08 9.14E+05 1.90E+05 2.35 E+04 4.29E-01 0.OOE+00 1.78E-03 2.79E+03 1.36E+05 1.69E+04 5.74E+04 9.84E+04 2.49E+04 1.92E+04 4.81 E+04 1.66E+04 6.51 E+05 6.51 E+04 9.07E+05 7.40E+04 6.44E+02 3.92E+04 6.77E+06 Liver 1.12E+03 1.14E+05 0.OOE+00 4.29E+04 3.34E+04 9.03E+02 1.77E+03 1.3 IE+04 1.13E+05 1.50E+04 1.98E+05 0.OOE+00 0.OOE+00 0.0OE+00 4.18E+04 9.1 8E+03 7.70E-02 1.72E+02 3.48E-03 0.OOE+00 0.00E+00 1.14E+04 7.40E+02 7.59E+02 8.5 5E+03 6.85E+03 4.8 ]E+04 2.03E+04 1.0 IE+06 1.7 1E+05 8.25E+05 6.4 8E+01 2.2 5E+02 1.95E+04 2.12E+06 T. Body 1.12E+ 03 9.88E+04 1.54E+02 9.51 E+ 03 1.67E+04 1.07E+03 3.16E+ 03 2.26E+04 7.03E+04 3.14E+04 1.14E+05 1.72E+04 6.44E+06 2.44E+04 3.70E+04 6.55 E+ 03 3.60E-02 4.26E+01 5.77 E-02 1.07 E+ 03 1.69E+04 9.14E+ 03 2.OOE+04 2.07E+04 3.02 E+ 03 3.04E+03 2.73E+04 7.70 E+ 03 2.25 E+ 05 1.16E+05 1.28E+05 4.33 E+ 03 7.55E+01 2.90 E+ 03 3.61E+05 Thyroid 1.12E+03 0.OOE+00 8.55E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.I5E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.26E+02 9.1OE+01 6.07E+03 6.33E+03 1.62E+07 3.85E+06 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 1.12E+03 0.00E+00 2.43 E+0 1 1.00E+04 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 7.14E+04 1.97E+04 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 5.96E+04 8.62E+03 8.55E-02 3.92E+02 5.07E-02 7.03E+03 1.84E+05 2.12E+04 0.00E+00 0.00E+00 6.36E+04 5.03 E+04 7.88E+04 3.38E+04 3.30E+05 9.55E+04 2.82E+05 2.11E+01 0.OOE+00 8.55E+03 1.17E+06 Lung 1.12E+03 0.00E+00 1.70E+04 1.58E+06 1.27E+06 5.07E+05 1.1 ]E+06 7.07E+06 9.95E+05 7.45E+04 O.00E+00 2.16E+06 1.48E+07 2.63E+06 2.23E+06 6.14E+05 3.42E+03 1.35E+05 9.5 1Er02 6.62E+05 1.43E+07 5.48E+06 3.24E+06 2.32E+06 1.48E+06 1.76E+06 0.OOE+00 0.OOE+00 1.2 1E+05 1.45E+04 1.04E+05 1.74E+06 1.83E+05 5.44E+05 1.20E+07 GI-LLI

1. 12E+03 4.22E+04 1.08E+03 2.29E+04 7.07E+04 1.32E+04 3.44E+04 9.62E+04 1.63 E+04 1.58E+04

7. 99E+03 1.67E+05 3.43E+05

1. 84E+05 6.11E+04 3.70E+04

2. 78E+04 1.27E+05 4.81E+03 4.48E+04 4.29E+05 1.00E+05 1.64E+05 4.03E+04

7. 14E+04 1.82E+05 2.84E+03 5.48E+03 3.85E+03 4.18E+03 3.62E+03

1. 02 E+05 2.26E+05 5.66E+04 3.89E+05 Calculated per ODCM equation 2.3.22

IProcedure Number:

Beaver Valley Power Station

.o 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

97 of 133 ATTACHMENT J Page 4 of 19 P&I ORGAN DOSE FACTORS Table 2.3-5 R VALUES FOR BEAVER VALLEY SITE (mrmn/yr per uCi/cu rreter)

Pathway = Inhalation Age Group= Infant Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-1 40 La-140 Ce-141 Ce-144 Bone 0.OOE+00 2.03E+06 O.OOE+00 o.00E+00 1.36E+04 0.00E+00 O.00E+00 O.OOE+O0 1.93E+04 7.77E+03 0.OOE+00 3.98E+05 4.09E+07 5.88E+05 1.15E+05 1.57E+04 3.42E-01 0.OOE+00 1.40E-03 2.02E+03 8.68E+04 9.98E+03 3.79E+04 5.17E+04 1.67E+04 1.41 E+04 3.79E+04 1.32E+04 3.96E+05 4.83E+04 5.49E+05 5.60E+04 5.05E+02 2.77E+04 3.19E+06 Liver 6.47E+02 1.1 2E+05 0.OOE+00 2.53E+04 2.3 5E+04 6.5 1E+02 1.22E+03 8.02E+03 6.26E+04 5.67E+03 1.90E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.79E+04 6.43E+03 7.29E-02 1.65E+02 2.88 E-03 0.00E+00 0.OOE+00 7.22E+03 5.56E+02 4.77E+02 6.90E+03 6.09E+03 4.44E+04 1.92E+04 7.03E+05 1.3 5E+05 6.12E+05 5.60E+01 2.OOE+02 1.67E+04 1.21E+06 T. Body 6.47E+02 7.74E+ 04 8.95E+01 4.98 E+ 03 9.48 E+ 03 6.41 E+ 02 1.82E+03 1.18 E+ 04 3.11 E+ 04

1. 19E+ 04 8.82E+04 1.14E+ 04 2.59E+ 06 1.57E+04 2.03E+04 3.78 E+ 03 2.63 E-02 3.23E+01 3.72E-02 6.79 E+ 02 1.09E+04 5.OOE+03 1.20E+ 04 1.09E+04 2.07 E+ 03 2.23 E+ 03 1.96E+04 5.60E+03 7.45 E+ 04 5.29E+04 4.55 E+ 04 2.90E+03 5.15 E+ 01 1.99E+03 1.76E+05 Thyroid 6.47E+02 0.OOE+00 5.75E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.35E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 1.0 IE+02 6.23E+01 4.87E+03 4.2 IE+03 1.48E+07 3.56E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 6.47E+02 0.00E+00 1.32E+01 4.98E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3,25E+04 7.46E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.11 E+04 4.72E+03 5.70E-02 2.65 E+02 3.11E-02 4.24E+03 1.07E+05 1.09E+04 0.00E+00 0.00E+00 3.75E+04 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 0.OOE+00 5.25 E+03 5.38E+05 Lung 6.47E+02 0.00E+00 1.28E+04 1.00E+06 1.0 1E+06 3.79E+05 7.77E+05 4.5 IE+06 6.47E+05 2.82E+04 0.00E+00 2.03E+06 1.12E+07 2.45E+06 1.75E+06 4.79E+05 3.32E+03 1.35E+05 8.1 IE+02 5.52E+05 1.16E+07 3.67E+06 2.65E+06 1.64E+06 1.3 IE+06 1.68E+06 0.OOE+00 0.OOE+00 7.97E+04 1.18E+04 7.13E+04 1.60E+06 1.68E+05 5.17E+05 9.84E+06 GI-LLI 6.47E+02 1.61E+04 3.57E+02 7.06E+03 2.48E+04 4.86E+03 1.11E+04 3.19E+04 5.14E+04 5.98E+03 3.04E+03 6.40E+04

1. 31 E+05 7.03E+04 2.17 E+04 1.27E+04 2.69E+04 4.87E+04 2.03 E+03

1. 61 E+04 1.64E+05

3. 30E+04 5.91 E+04

1. 47 E+04 2.73E+04 6.90E+04 1.06E+03 2.16E+03 1.33 E+03 1.43 E+03 1.33E+03

3. 84E+04 8.48E+04 2.16E+04 1.48E+05 Calculated per ODCM equation 2.3-22

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02 Title-Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 98 of 133 ATTACHMENT J Page 5 of 19 P&I ORGAN DOSE FACTORS Table 2.3-6 R VALUES FOR BEAVER VALLEY SITE (sq mete-mrem/yr per uCi/cu meter)

Pathway = Ground 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P-32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Z r-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 0.OOE+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15E+10 7.47E+08 4.51 E+08 8.99E+06 2.16E+04 0.OOE+00 1.07E+06 2.45 E+08 1.37E+08 0.OOE+00 4.OOE+06 1.84E+05 1.08E+08 4.22E+08 3.44E+09 0.OOE+00 0.OOE+00 9.17E+04 1.98E+07 1.72E+07 2.45E+06 6.86E+09 1.51E+08 1.03E+10 2.05E+07 1.92E+07 1.37E+07 6.96E+07 Liver 0.OOE+00 0.OOE+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15E+10 7.47E+08 4.5 1E+08 8.99E+06 2.16E+04 0.OOE+00 1.07E+06 2.45E+08 1.37E+08 0.OOE+00 4.OOE+06 1.84E+05 1.08E+08 4.22E+08 3.44E+09 0.OOE+00 0.OOE+00 9.17E+04 1.98E+07 1.72E+07' 2.45E+06 6.86E+09 1.51E+08 1.03E+1 0 2.05E+07 1.92E+07 1.37E+07 6.96E+07 T. Body 0.OOE+00 0.00E+ 00 4.66E+06

!.39E+09 2.73 E+ 08 0.OOE+00 3.79 E+ 08 2.15 E+ 10 7.47 E+ 08 4.51 E+ 08 8.99E+ 06 2.16E+ 04 0.OOE+00 1.07E+06 2.45 E+ 08 1.37E+08 0.00 E+ 00 4.00E+ 06 1.84E+05 1.08E+08 4.22 E+ 08 3.44 E+ 09 0.OOE+00 0.00E+00 9.17E+ 04 1.98E+07 1.72 E+ 07 2.45E+06 6.86E+09 1.51 E+ 08 1.03E+ 10 2.05 E+ 07 1.92E+07 1.37E+07 6.96E+07 Thyroid 0.OOE+00 0.OOE+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15E+10 7.47E+08 4.5 1E+08 8.99E+06 2.16E+04 0.OOE+00 1.07E+06 2.45E+08 1.37E+08 0.OOE+00 4.OOE+06 1.84E+05 1.08E+08 4.22E+08 3.44E+09 0.00E+00 0.OOE+00 9.1 7E+04 1.98E+07 1.72E+07 2.45E+06 6.86E+09 1.5 IE+08 1.03E+10 2.05E+07 1.92E+07 1.37E+07 6.96E+07 Kidney 0.OOE+00 0.OOE+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15 E+ 10 7.47E+08 4.51 E+08 8.99E+06 2.16 E+04 0.00E+00 1.07E+06 2.45 E+0 8 1.37E+08 0.00E+00 4.00E+06 1.84E+05 1.08E+08 4.22E+08 3.44E+09 0.00E+00 0.00E+00 9.17E+04 1.98 E+0 7 1.72E+07 2.45 E+06 6.86 E+09 1.51E+08 1.03E+ 10 2.05 E+07 1.92E+07 1.37E+07 6.96E+07 Lung 0.OOE+00 0.OOE+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15E+10 7.47E+08 4.5 1E+08 8.99E+06 2.16E+04 0.0 OE+00 1.07E+06 2.45E+08 1.37E+08 0.OOE+00 4.OOE+06 1.84E+05 1.08E+08 4.22E+08 3.44E+09 0.OOE+00 0.OOE+00 9.17E+04 1.98E+07 1.72E+07 2.45E+06 6.86E+09 1.5 1E+08 1.03E+10 2.05E+07 1.92E+07 1.37E+07 6.96E+07 GI-LLI 0.00E+00 0.00E+00 4.66E+06 1.39E+09 2.73E+08 0.OOE+00 3.79E+08 2.15 E+ 10 7.47E+08 4.51 E+08 8.99E+06

2. 16E+04 0.OOE+00 1.07E+06 2.45E+08 1.37E+08 0.OOE+00 4.00 E+0 6

1. 84E+05 1.08E+08 4.22E+08 3.44E+09 0.00E+00 0.00E+00 9.17E+04 1.98E+07

1. 72 E+07 2.45 E+-06 6.86E+09 1.51 E+0 8 1.03E+1 0 2.05E+07 1.92E+07 1.37E+07 6.96E+07 Calculated per ODCM equation 2.3-23

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1_3 1_99 of] 133 ATTACHMENT J Page 6 of 19 P&I ORGAN DOSE FACTORS P&I ORGAN DOSE FACTORS Table 2.3-7 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway = Vegetation Age Group= Adult 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P-32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-13 6 Cs-137 Ba-I 40 La-140 Ce-141 Ce-144 Bone 0.OOE+00 1.40E+09 0.00E+00 0.OOE+00 1.26E+08 0.OOE+00 0.OOE+00 0.003E+00 3.17E+08 4.91E+08 0.OOE+00 9.97E+09 6.05E+11 5.I1E+06 1.17E+06 1.42E+05 2.1 6E-06 0.OOE+00 3.10E+00 4.77E+06 1.93 E+08 1.05E+07 1.04E+08 1.37E+08 3.49E+08 2.51 E+08 8.08E+07 2.09E+06 4.67E+09 4.27E+07 6.36E+09 1.29E+08 1.98E+03 1.97E+05 3.29E+07 Liver 2.26E+03 8.74E+07 0.OOE+00 3.13E+08 2.96E+08 1.17E+07 3.07E+07

).67E+08 1.0 ]E+09 3.1 1E+08 2.19E+08 0.OOE+00 0.OOE+00 0.0OE+00 3.77E+05 7.92E+04 5.46E-07 6.15E+06 8.77E+00 0.OOE+00 0.OOE+00 9.75E+06 1.96E+06 1.53E+06 1.25E+08 9.3 8E+0 7 1.16E+08 3.63E+06 1.1 1E+10 1.69E+08 8.70E+09 1.6 IE+05 9.97E+02 1.33E+05 1.3 8E+07 T. Body 2.26 E+ 03 5.43 E+ 07 4.64 E+ 04 5.97 E+ 07 1.14E+ 08 1.95 E+ 07 6.89E+ 07 3.69E+ 08 4.56E+08 6.16E+ 08 1.02 E+ 08 2.86E+ 08 1.48E+ 11 1.37 E+ 05 2.55 E+ 05 4.26 E+ 04 1.99E-07 1.17E+ 06 1.12E+ 02 2.06 E+ 06 2.44 E+ 07 5.79 E+ 06 4.11 E+ 07 3.25 E+ 07 4.26 E+ 07 3.98E+ 07 6.62E+ 07 1.11 E+ 06 9.08E+09 1.21E+ 08 5.70E+ 09 8.42 E+ 06 2.63 E+ 02 1.51E+04 1.77 E+ 06 Thyroid 2.26E+03 0.0OE+00 2.78E+04 0.0OE+00 0.0OE+00 0.0OE+00 0.0OE+00 0.OOE+00 0.OOE+00 2.68E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.5 IE+05 1.39E+05 8.92E+07 8.64E+07 3.79E+ 10 5.33E+08 0.00E+00 0.0OE+00 0.0OE+00 0.0OE+00 0.0OE+00 0.0OE+00 0.0OE+00 Kidney 2.26E+03 0.OOE+00 1.02E+04 9.31E+07 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 6.75E+08 4.55E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.91 E+0 5 7.83 E+04 6.37E-07 1.39E+07 1.33E+02 1.82E+07 3.72 E+0 8 1.92E+07 0.OOE+00 0.OOE+00 1.42E+09 1.05 E+09 1.98E+08 6.33E+06 3.59E+09 9.38 E+0 7 2.95 E+09 5.49 E+04 0.00E+00 6.19 E+04 8.16 E+0 6 Lung 2.26E+03 0.OOE+00 6.16E+04 0.OOE+00 8.28E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.93E+08 0.0OE+00 0.0OE+00 0.0OE+00 0.001E+00 0.0OE+00 0.OOE+00 0.0OE+00 0.OOE+00 4.30E+00 0.001E+00 0.00E+00 0.OOE+00 8.07E+07 1.05E+08 0.OOE+00 0.OOE+00 0.0OE+00 0.00E+00 1.19E+09 I.29E+07 9.8 IE+08 9.24E+04 0.001E+00 0.OOE+00 0.OOE+00 G I-LL I 2.26E+03

1. 58E+08

1. 17E+07

9. 59E+08

9. 88E+08 2.97E+08 6.23 E+08 3.14E+09 6.36E+08 4.14E+08 4.33E+07

1. 60 E+09

1. 75 E+ 10 2.81E+09

1. 19E+09 4.81E+08 2.02E-03 1.43E+07 5.19E+03 5.57 E+08 1.25 E+ 10 3.98E+09 2.94E+09

1.

50E+09

1. 17E+09

1. 27 E+09 3.05 E+07 3.26E+06 1.94E+08 1.91E+07

1. 68 E+08 2.65E+08 7.32E+07

5. 10E+08 1.11 E+ 10 All nuclides (except H-3) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level OfeUse:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3 1

100 of 133 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 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.00E+00 1.61E+09 o.OOE+00 0.OOE+00 1.79E+08 O.OOE+00 O.OOE+00 0.OOE+00 4.24E+08 5.94E+08 0.OOE+00 1.51E+10 7.51E+11 7.84E+06 1.72E+06 1.92E+05 2.0OE-06 0.OOE+00 2.74E+00 6.82E+06 2.38E+08 1.52E+07 1.54E+08 2.14E+08 5.52E+08 3.62E+08 7.69E+07 1.94E+06 7.10E+09 4.38E+07 1.01E+10 1.38E+08 1.81E+03 2.83E+05 5.27E+07 Liver 2.59E+03 9.98E+07 0.OOE+00 4.54E+08 4.19E+08 1.79E+07 4.36E+07 2.49E+08 1.47E+09 3.77E+08 2.74E+08 0.OOE+00 0.OOE+00 0.OOE+00 5.43E+05 1.07E+05 4.97E-07 5.65E+06 7.64E+00 O.OOE+00 0.OOE+00 1.43E+07 2.84E+06 2.34E+06 1.96E+08 1.34E+08 1.08E+08 3.29E+06 1.67E+10 1.72E+08 1.35E+10 1.69E+05 8.88E+02 1.89E+05 2.18E+07 T. Body 2.59E+ 03 6.24E+07 6.17E+ 04 9.01 E+07 1.62E+08 3.00E+07 1.00E+08 5.60E+ 08 6.87E+08 7.47E+08 1.29 E+ 08 4.34 E+ 08 1.85E+ 1I 2.10E+05 3.74 E+ 05 5.87E+ 04 1.81 E-07 1.08E+06 9.90E+ 01 2.92E+ 06 3.90E+07 8.72E+06 6.02E+07 5.01 E+ 07 6.56 E+ 07 5.73 E+ 07 5.78E+07 1.00E+06 7.75 E+ 09 1.16E+08 4.69E+09 8.90E+06 2.36E+02 2.17E+ 04 2.83E+06 Thyroid 2.59E+03 0.OOE+00 3.43E+04 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.24E+08 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE÷00 0.OOE+00 0.OOE+00 0.OOE+00 3.50E+05 2.05E+05 1.3 IE+08 1.17E+08 3.14E+10 4.59E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Kidney 2.59E+03 0.OOE+00 1.35E+04 1.36E÷08 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 9.42 E+0 8 5.51 E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.98E+05 1.03E+05 5.81E-07 1.29E+0 7 1.14E+02 2.41 E+07 5.97E+0 8 2.74 E+0 7 0.00E+00 0.00E+00 2.24E+09 1.51 E+09 1.85E+08 5.77E+06 5.31E+09 9.37E+07 4.59E+09 5.74E+04 0.OOE+00 8.90E+04 1.30E+07 Lung 2.59E+03 0.OOE+00 8.8 1E+04 O.OOE+00 1.32E+08 0.OOE+00 0.OOE+00 o.OOE+00 o.OOE+00 4.77E+08 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.24E+00 0.OOE+00 0.OOE+00 o.OOE+00 1.35E+08 1.88E+08 0.OOE+00 0.OOE+00 0.0OE+00 0.0OE+00 2.03E+09 1.48E+07 1.78E+09 1.14E+05 0.OOE+00 0.OOE+00 0.0OE+00 GI-LLI 2.59E+03 1.35E+08 1.04E+07

9. 32E+08 9.90E+08 3.33 E+08

6. 01 E+08 3.24E+09 6.23 E+08 5.02E+08 4.05E+07

1. 80 E+09 2.11 E+1 0 3.21 E+09 1.25E+09 4.56E+08

1. 19E-02 1.01 E+07 5.02E+03 5.70E+08 1.48E+10 4.03 E+09 3.11E+09 1.67E+09 1.37E+09 1.36E+09 2.13E+07 2.49E+06 2.08E+08 1.39E+07 1.92E+08 2.13E+08 5.10E+07 5.41 E+08 1.33E+ 10 All nuclides (except H-3) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 101 of 133 ATTACHMENT J Page 8 of 19 P&I ORGAN DOSE FACTORS Table 2.3-9 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrern/yr per uCi/sec)

Pathway = Vegetation Age Group= Child 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-5 9 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m.

Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone O.OOE+00 3.37E+09 0.00E+00 0.OOE+00 3.98E+08 0.OOE+00 0.OOE+00 0.OOE+00 8.13E+08 4.91 E+08 0.OOE+00 3.60E+10 1.24E+12 1.86E+07 3.86E+06 4.11 E+05 3.65E-06 O.OOE+00 4.71E+00 1.53E+07 7.45 E+08 3.21 E+07 3.52E+08 4.99E+08 1.32E+09 8.41 E+08 1.43E+08 3.53E+06 1.60E+10 8.24E+07 2.39E+10 2.77E+08 3.25 E+03 6.56E+05 1.27E+08 Liver 4.01E+03 1.58E+08 0.OOE+00 6.65E+08 6.43E+08 2.99E+07 6.44E+07 3.78E+08 2.1 7E+09 3.1 ]E+08 4.52E+08 0.OOE+00 0.OOE+00 0.OOE+00 8.48E+05 1.60E+05 6.59E-07 7.7 1E+06 9.24E+00 0.OOE+00 0.OOE+00 2.17E+07 4.5 7E+06 3.85E+06 3.56E+08 2.3 5E+0 8 1.44E+08 4.37E+06 2.63E+ 10 2.27E+08 2.29E+10 2.42E+07 1.13E+03 3.27E+05 3.98E+07 T. Body 4.01E+03 1.30E+08

1. 17E+ 05 1.77E+08 3.20E+ 08 6.04 E+ 07 1.97 E+ 08 1.12E+09 1.35E+09 6.16E+08 2.78 E+ 08 1.03 E+ 09 3.15 E+ 11 4.99E+05 7.55 E+ 05 1.14E+05 3.08E-07 1.91 E+ 06 1.53 E+ 02 5.90 E+ 06 9.30E+07 1.73 E+ 07 1.23 E+ 08 1.05E+08 1.57E+08 1.31 E+ 08 8.17E+07 1.65E+06 5.55 E+ 09 1.47E+08 3.38E+09 1.62E+07 3.83 E+ 02 4.86E+05 6.78E+06 Thyroid 4.01E+03 0.OOE+00 6.50E+04 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.68E+08 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.77E+05 4.63E+05 3.16E+08 2.7 IE+08 4.76E+10 8.12E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 4.01 E+03 0.00E+00 1.78E+04 1.86E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.36E+09 4.55 E+0 8 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.21 E+06 1.50E+05 7.31E-07 1.65E+07 1.34E+02 3.86E+07 1.01 E+09 4.04E+07 0.OOE+00 0.00E+00 3.77 E+09 2.47E+09 2.36E+08 7.28E+06 8.15E+09 1.21 E+08 7.46 E+09 7.89E+04 0.00E+00 1.43 E+05 2.21 E+07 Lung 4.01E+03 0.OOE+00 1.19E+05 0.OOE+00 1.87E+08 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.93E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.69E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.95E+08 2.78E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.93E+09 1.80E+07 2.68E+09 1.45E+05 0.0OE+00 0.0OE+00 0.OOE+00 GI-LLI 4.01E+03 9.32E+07 6.21 E+06 5.58E+08 6.70E+08 2.45E+08 3.76E+08

2. 10E+09 3.80E+08 4.14E+08 2.91 E+07 1.39E+09 1.67E+10 2.48E+09 8.85E+08 2.96E+08 2.03E-01 6.38E+06 5.26E+03 3.97E+08

1. 16E+ 10 2.58E+09 2.20E+09

1. 19E+09 1.07E+09 1.03 E+09 1.28E+07 1.76E+06 1.42E+08 7.96E+06 1.43 E+0 8 1.40 E+0 8 3.16E+07 4.08E+08 1.04E+10 All nuclides (except H-3) calculated per ODCM equation 2.3-26 H-3 calculated per ODCM equation 2.3-29

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 102 of 133 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/sec)

Pathway = M eat Age Group= Adult Nucide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-1 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-1 40 La-140 Ce-141 Ce-144 Bone 0.OOE+00 3.95E+09 0.OOE+00 0.OOE+00 2.14E+08 0.OOE+00 O.OOE+00 0.OOE+00 2.54E+08 1.15E+08 0.OOE+00 2.41 E+08 8.41 E+09 8.94E+05 1.47E+06 1.89E+06 0.OOE+00 3.83E-21 8.57E+07 1.97E+09 4.77E+06 0.OOE+00 0.OOE+00 8.38E+08 9.33 E+08 9.13E+06 3.12E-01 4.53 E+08 1.02E+07 5.90E+08 2.44E+07 3.16E-02 i.16E+04 1.03E+06 Liver 3.25E+02 2.46E+08 0.OOE+00 6.49E+06 5.04E+08 4.01E+06 1.42E+07 5.12E+07 8.09E+08 7.27E+07 4.1 1E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.7 1E+05 1.05E+06 8.5 IE+04 1.08E-20 0.OOE+00 0.OOE+00 4.4 IE+06 0.OOE+00 0.OOE+00 3.0OE+08 3.48E+08 1.3 IE+07 5.42E-01 1.08E+09 4.04E+07 8.06E+08 3.06E+04 1.59E-02 7.83E+03 4.32E+05 T. Body 3.25E+02 1.53E+08 5.86E+ 03 1.24E+06 1.93E+08 6.66E+ 06 3.18E+ 07 1.13E+08 3.66 E+ 08 1.44E+ 08 1.92E+ 08 6.92 E+ 06 2.06E+09 2.39E+04 3.19E+ 05 5.64 E+ 05 1.62E+04 1.38E-19 3.69E+07 2.49E+08 2.62E+06 0.00E+00 0.00E+00 1.02E+08 1.48E+08 7.48E+06 1.65E-01 8.81E+08 2.91E+07 5.28E+08 1.60E+06 4.21E-03 8.88E+02 5.55E+04 Thyroid 3.25-E+02 0.OOE+00 3.50E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.25E+07 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 2.14E+08 3.2 IE+08 4.28E+09 7.96E+0 1 0.0OE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.0OE+00 0.OOE+00 Kidney 3.25E+02 0.00E+00 1.29E+03 1.93E+06 0.OOE+00 O.OOE+O0 0.OOE+00 0.OOE+00 5.41 E+08 1.06E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.39 E+0 5 1.04E+06 1.93E+05 1.64E-19 3.27 E+0 8 3.80E+09 8.67 E+06 0.00E+00 0.OOE+00 3.40E+09 3.89E+09 2.24E+07 9.46E-01 3.49E+08 2.25E+07 2.74 E+08 1.04E+04 0.OOE+00 3.64E+03 2.56E+05 Lung 3.25E+02 0.OOE+00 7.78E+03 0.OOE+00 1.4 1E+08 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 9.18E+07 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+00 5.30E-21 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 1.16E+08 3.08E+06 9.1OE+07 1.75E+04 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 3.25 E+02 4.44E+08 1.47E+06 1.99E+07 1.68E+09 1.02E+08 2.87E+08 9.61E+O8 5.10E+08 9.67E+07 8.11 E+07 3.87E+07 2.43E+08 4.92E+08 1.49E+09 6.37E+09 1.97E+05 6.40E-18 1.00E+10 1.27E+1 I 1.80E+09 O.OOE+00 O.OOE+00

2. 81 E+09 4.70E+09 3.45E+06 4.87E-01 1.89E+07 4.59E+06 1.56E+07 5.02E+07

1. 17E+03 2.99E+07 3.50E+08 All nuclides (except H-3) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30

Procedure Number:

yPower Station 1/2-ODC-2.02 Title-Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1_3 103 of 133 ATTACHMENT J Page 10 of 19 P&I ORGAN DOSE FACTORS Table 2.3-1 1 R VALUES FOR BEAVER VALLEY SITE (sq meter-mremnyr per uCi/sec)

Pathway = M eat Age Group= Teen 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-1 10m Sb-124 Sb-125 Te-127m Te-129in 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-I140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 3.34E+09 0.OOE+00 0.OOE+00 1.71 E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.79E+08 7.69E+07 0.OOE+00 2.03 E+08 5.44E+09 7.53E+05 1.18E+06 1.47E+06 0.OOE+00 3.04E-21 6.98E+07 1.28E+09 3.61 E+06 0.OOE+00 0.OOE+00 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 Liver 1.94E+02 2.07E+08 0.00E+00 4.95E+06 4.OOE+08 3.22E+06 1.09E+07 3.97E+07 6.21E+08 4.89E+07 3.43E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.71E+05 8.17E+05 7.03E+04 8.4 8E-2 I 0.OOE+00 0.OOE+00 3.42E+06 0.OOE+00 0.OOE+00 2.5 1E+08 2.90E+08 1.06E+07 4.42E-0 1 8.48E+08 3.14E+07 6.5 ]E+08 2.47E+04 1.28E-02 6.49E+03 3.61E+05 T. Body 1.94E+02 1.29E+ 08 4.69 E+ 03 9.81 E+ 05 1.54 E+ 08 5.40E+ 06 2.52E+07 8.95 E+ 07 2.90E+ 08 9.66E+07 1.61 E+ 08 5.83 E+ 06 1.34 E+ 09 2.02 E+ 04 2.55E+05 4.50E+05 1.34E+04 1.10E-19 2.98 E+ 07 2.09E+08 2.08 E+ 06 0.00E+ 00 0.00E+00 8.41 E+ 07 1.24E+08 5.71 E+ 06 1.35E-01 3.93 E+ 08 2.11 E+ 07 2.27E+08 1.30E+06 3.40E-03 7.46 E+ 02 4.68E+04 Thyroid 1.94E+02 0.OOE+00 2.60E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.20E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.68E+08 2.52E+08 3.1OE+09 6.17E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 1.94E+02 0.00E+00 1.03E+03 1.48E+06 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 3.97E+08 7.14E+07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.45 E+05 7.92 E+0 5 1.61E+05 1.26E-19 2.46E+08 3.19E+09 6.52E+06 0.00E+00 0.00E+00 2.87E+09 3.27E+09 1.83E+07 7.75 E-01 2.69E+08 1.71E+07 2.22E+08 8.38E+03 0.00E+00 3.06E+03 2.15E+05 Lung 1.94E+02 0.OOE+00 6.69E+03 0.OOE+00 1.26E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.17E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.71E-21 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.0OE+00 0.OOE+00 1.03E+08 2.69E+06 8.6 IE+07 1.66E+04 0.OOE+00 0.0OE+00 0.OOE+00 GI-LLI 1.94E+02

2. 80E+08

7. 88E+05

1. 01 E+07 9.45 E+08

6. 01 E+07 1.51E+08 5.17E+08 2.63 E+08 6.50E+07

.5.08E+07 2.42E+07 1.53E+08 3.09E+08 8.56E+08 3.49E+09 1.26E+05 5.57 E-18 5.83E+09 7.94E+ 10 9.60E+08 0.00E+00 0.OOE+00 1.76E+09 2.93E+09 2.10E+06 3.34E-01 1.05E+07 2.53 E+06 9.27E+06

3. il E+07 7.33E+02

1. 86 E+07

2. 19E+08 All nuclides (except H-3) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3 10O4 of 133 ATTACHMENT J Page I I 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 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32

.33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m.

Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-1 40 La-140 Ce-141 Ce-144 Bone 0.OOE+00 6.29E+09 0.OOE+00 0.OOE+00 3.04E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.68E+08 4.65E+07 0.OOE+00 3.85E+08 7.03 E+09 1.42E+06 2.09E+06 2.54E+06 0.OOE+00 5.33E-21 1.26E+08 3.12E+09 5.99E+06 0.OOE+00 0.OOE+00 1.33E+09 1.47E+09 1.41E+07 4.84E-01 6.35E+08 1.38E+07 9.02E+08 3.72 E+07 4.76E-02 1.83E+04 1.64E+06 Liver 2.34E+02 2.94E+08 0.OOE+00 5.66E+06 4.91E+08 4.21E+06 1.28E+07 4.72E+07 7.15E+08 2.95E+07 4.87E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.59E+05 9.90E+05 9.79E+04 1.05E-20 0.OOE+00 0.OOE+00 4.04E+06 0.0OE+00 0.00E+00 3.59E+08 4.1 IE+08 1.42E+07 5.99E-01 1.04E+09 3.78E+07 8.63E+08 3.26E+06 1.66E-02 9.13E+03 5.15E+05 T. Body 2.34E+02 2.43 E+ 08 7.31 E+03 1.51E+06 2.45 E+ 08 8.52E+06 3.91E+07 1.39E+08 4.44E+ 08 5.84 E+ 07 2.99E+08 1.10E+07 1.78E+09 3.81E+04 4.09E+ 05 7.07E+05 2.42E+04 1.73E-19 4.85 E+ 07 3.89E+08 3.23 E+ 06 0.00E+00 0.OOE+00 1.58E+08 2.29E+ 08 8.04E+06 2.27E-01 2.20E+08 2.45 E+ 07 1.27 E+ 08 2.17E+06 5.61 E-03 1.36E+04 8.77E+04 Thyroid 2.34E+02 0.OOE+00 4.06E+03 0.0OE+00 0.0OE+00 0.0OE+00 0.0OE+00 0.OOE+00 0.OOE+00 2.54E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.19E+08 4.75E+08 4.68E+09 1.1 IE+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 2.34E+02 0.00E+00 1.11E+03 1.59E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.50E+08 4.32E+07 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 6.57E+05 9.30E+05 2.09 E+0 5 1.52 E-19 3.18 E+0 8 4.21E+0 9 7.53 E+0 6 0.00E+00 0.00E+00 3.80E+09 4.33E+09 2.32E+07 9.98E-01 3.23E+08 2.01E+07 2.81 E+08 1.06E+04 0.00E+00 4.00E+03 2.85E+05 Lung 2.34E+02 0.OOE+00 7.41E +03 0.OOE+00 1.42E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.73E+07 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 5.3 1E-21 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.16E+08 3.OOE+06 1.0 1E+08 1.94E+04 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 2.34E+02

1. 74 E+08 3.88E+05 4.75 E+06 5.12 E+08 3.45E+07 7.45E+07 2.61 E+08 1.25E+08 3.93 E+07 3.13E+07 1.49E+07 9.47E+07

1. 90 E+08 4.79E+08 1.83 E+09 8.09E+04 5.95 E-18 3.26E+09 4.85 E+ 10 4.81E+08 0.OOE+00 0.00E+00 1.08E+09 1.80E+09 1.26E+06 2.41 E-01 5.62E+06 1.33E+06 5.40E+06 1.89E+07 4.63E+02 1.14 E+07 1.34E+08 All nuclides (except H-3) calculated per ODCM equation 2.3-25 H-3 calculated per ODCM equation 2.3-30

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 105 of 133 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 H-3 P-32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.00E+00 1.45E+10 O.00E+00 0.OOE+00 2.40E+07 0.OOE+00 0.OOE+00 0.00E+00 9.80E+08 1.85E+09 0.OOE+00 1.16E+09 3.16E+10 6.78E+03 7.40E+02 6.77E+04 2.8 1E-12 0.OOE+00 2.83E+00 8.29E+02 1.43E+04 4.16E+07 0.OOE+00 0.OOE+00 3.44E+07 4.95 E+07 2.52E+08 3.29E+06 3.89E+09 2.23E+08 4.99E+09 2.28E+07 3.84 E+00 3.99E+03 2.54E+05 Liver 7.63E+02 9.01E+08 0.OOE+00 5.95E+06 5.63E+07 9.1OE+05 3.67E+06 1.12E+07 3.12E+09 1.1 7E+09 2.19E+09 0.OOE+00 0.OOE+00 0.OOE+00 2.37E+02 3.77E+04 7.11 E-13 2.1 1E+07 7.99E+00 0.OOE+00 0.OOE+00 3.84E+07 0.OOE+00 0.OOE+00 1.23E+07 1.85E+07 3.60E+08 5.72E+06 9.27E+09 8.82E+08 6.82E+09 2.87E+04 1.93E+00 2.70E+03 1.06E+05 T. Body 7.63 E+02 5.60E+ 08 2.38E+04 1.13 E+ 06 2.16E+ 07 1.51E+06 8.22 E+ 06 2.46E+ 07 1.41 E+09 2.32E+09 1.02E+09 3.33 E+ 07 7.76 E+ 09 1.81E+02 1.61 E+ 02 2.03 E+04 2.60E-13 4.01 E+06 1.02 E+ 02 3.57E+02 1.81 E+03 2.28 E+ 07 0.OOE+00 0.OOE+00 4.19E+ 06 7.84E+ 06 2.06 E+ 08 1.75E+06 7.58E+09 6.35E+08 4.47E+09 1.49E+06 5.11E-01 3.06E+02 1.36E+04 Thyroid 7.63E+02 0.OOE+00 i.42E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.0 1E+09 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.79E+06 1.70E+07 1.1 8E+l 1 8.4 IE+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 7.63E+02 O.OOE+00 5.24E+03 1.77E+06 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.09E+09 1.71 E+09 0.00E+00 0.00 E+00 0.00E+00 0.OOE+00 3.72E+02 3.72E+04 8.30E-13 4.77E+07 1.21 E+02 3.16E+03 2.77E+04 7.56E+07 0.OOE+00 0.OOE+00 1.40E+08 2.07E+08 6.17E+08 9.99E+06 3.OOE+09 4.91E+08 2.32 E+09 9.74E+03 0.OOE+00 1.25 E+03 6.29E+04 Lung 7.63E+02 0.OOE+00 3.15E+04 0.OOE+00 1.57E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.48E+09 0.0OE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 3.9 IE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.96E+08 6.73E+07 7.70E+08 1.64E+04 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 7.63E+02 1.63E+09

5. 98E+06

1. 82E+07 1.88 E+08 2.31E+07 7.43E+07

2. 10E+08 1.96E+09 1.56E+09 4.32E+08 1.86E+08 9.14E+08 3.73E+06 7.52E+05 2.29E+08 2.62E-09 4.88E+07 4.73E+03 9.68E+04 9.27E+05 1.57E+10 0.OOE+00 0.OOE+00

1. 15E+08 2.49E+08

9. 50E+07

5. 14E+06 1.62E+08 1:00E+08

1. 32 E+08 4.70E+07 1.42E+05 1.03E+07

8. 58E+07 All nuclides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

106 of 133 ATTACHMENT J Page 13 of 19 P&I ORGAN DOSE FACTORS Table 2.3-14 R VALUES FOR BEAVER VALLEY SITE (sq meter-mremlyr per uCi/sec)

Pathway = Cow Milk Age Group= Teen Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 2.67E+10 0.OOE+00 0.00E+00 4.18E+07 0.OOE+00 0.00E+00 0.OOE+00 1.51E+09 2.38E+09 0.OOE+00 2.14E+09 4.47E+10 1.25E+04 1.29E+03 1.16E+05 5.13E-12 0.OOE+00 4.90E+00 1.47E+03 2.03 E+04 6.87E+07 0.OOE+00 0.OOE+00 6.34E+07 9.06E+07 4.57E+08 6.01 E+06 6.76E+09 3.80E+08 9.05 E+09 4.12E+07 6.89E+00 7.32E+03 4.67E+05 Liver 9.94E+02 1.66E+09 0.OOE+00 9.91E+06 9.76E+07 1.60E+06 6.17E+06 1.89E+07 5.23E+09 1.5 1E+09 3.99E+09 0.OOE+00 0.OOE+00 0.OOE+00 4.08E+02 6.4 IE+04 1.27E-1 2 3.80E+07 1.37E+01 0.OOE+00 0.OOE+00 6.50E+07 0.OOE+00 0.OOE+00 2.25E+07 3.36E+07 6.39E+08 1.02E+07 1.5 9E+ 10 1.50E+09 1.20E+1 0 5.05E+04 3.39E+00 4.89E+03 1.93E+05 T. Body 9.94E+ 02 1.04E+09 4.15E+ 04 1.96E+06 3.77 E+ 07 2.68E+06 1.42E+07 4.26E+07 2.44E+09 2.99E+09 1.87E+09 6.12 E+ 07 1.10E+ 10 3.35E+02 2.81 E+ 02 3.53E+04 4.65E-13 7.25 E+ 06 1.77E+02 6.30E+02 3.32E+03 3.95 E+ 07 0.00 E+ 00 0.OOE+00 7.54 E+ 06 1.43E+07 3.43E+08 3.11 E+ 06 7.38E+09 1.01 E+ 09 4.19E+09 2.65E+06 9.01 E-01 5.62E+02 2.51E+04 Thyroid 9.94E+02 0.OOE+00 2.3 IE+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.30E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.5 1E+07 2.92E+07 1.87E+1 I 1.42E+09 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 9.94E+02 0.OOE+00 9.10E+03 2.95E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.34E+09 2.21E+09 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 6.00E+02 6.21 E+04 1.49E-12 8.70E+07 2.04E+02 5.20E+03 5.08E+04 1.24E+08 0.00E+00 0.00E+00 2.57E+08 3.79E+08 1.10E+09 1.79E+07 5.06E+09 8.15E+08 4.10E+09 1.71 E+04 0.00E+00 2.30E+03 1.15E+05 Lung 9.94E+02 0.OOE+00 5.93E+04 0.OOE+00 3.08E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.91E+09 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.59E+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 O.OOE+0O 1.93E+09 1.28E+08 1.59E+09 3.39E+04 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 9.94E+02 2.25E+09 6.97E+06 2.03E+07 2.31E+08 2.98E+07 8.51E+07 2.46E+08 2.21 E+09 2.01E+09 5.91E+08 2.55E+08 1.25 E+09

5. 11E+06 9.42E+05 2.74E+08 3.04E-08 6.81 E+07

8. 98E+03 1.23E+05

1. 26 E+06 1.83E+10 0.OOE+00 O.OOE+00 1.58E+08 3.40E+08 1.26E+08

7. 71 E+06 1.98E+08 1.20E+08

1. 71 E+08 6.35 E+07

1. 94 E+05 1.40E+07 1.17E+08 All nuclides (except H-3) calcalated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Beaver Valley Power SProcedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1

107 of 133 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 H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-1 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-I144 Bone 0.OOE+00 6.59E+10 0.OOE+00 0.OOE+00 9.70E+07 0.OOE+00 0.OOE+00 0.OOE+00 2.95E+09 1.97E+09 0.OOE+00 5.29E+09 7.55E+10 3.08E+04 3.OOE+03 2.61 E+05 1.25E-11 0.00E+00 1.12E+01 3.49E+03 6.49E+04 1.49E+08 0.OOE+00 0.OOE+00 1.56E+08 2.23E+08 1.11E+09 1.46E+07 1.56E+10 8.58E+08 2.18E+10 9.94E+07 1.65E+01 1.80E+04 1.15E+06 Liver 1.57E+03 3.09E+09 0.OOE+00 I.48E+07 1.57E+08 2.73E+06 9.43E+06 2.94E+07 7.87E+09 1.25E+09 7.40E+09 0.OOE+00 0.OOE+00 0.OOE+00 6.60E+02 1.02E+05 2.25E-12 6.92E+07 2.20E+01 0.OOE+00 0.OOE+00 1.01E+08 0.OOE+00 0.OOE+00 4.2 1E+0 7 6.24E+07 1.1 IE+09 1.8 1E+07 2.56E+ 10 2.36E+09 2.09E+10 8.71E+06 5.77E+00 8.99E+03 3.61E+05 T. Body 1.57E+03 2.54E+09 8.46 E+ 04 3.95E+06 7.82 E+ 07 5.52 E+ 06 2.89 E+ 07 8.67E+07 4.89 E+ 09 2.47E+ 09 4.55E+ 09 1.51E+08 1.91 E+ 10 8.24E+02 5.88E+02 7.26E+04 1.05E-12 1.71 E+ 07 3.65 E+ 02 1.34E+03 8.10E+03 8.05 E+ 07 0.00E+00 0.00E+00 1.86E+07 3.47E+07 6.33 E+ 08 6.83 E+ 06 5.40E+09 1.53E+09 3.08E+09 5.80 E+ 06 1.94E+00 1.34E+04 6.15E+04 Thyroid 1.57E+03 0.OOE+00 4.70E+04 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.07E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 3.74E+07 7.20E+07 3.68E+1 I 3.36E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 1.57E+03 0.00E+00 1.28E+04 4.16E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.96E+09 1.82E+09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.45 E+02 9.54E+04 2.50E-12 1.48E+08 3.20E+02 8.78 E+03 8.76E+04 1.87E+08 0.00E+00 0.00E+00 4.46E+08 6.56E+08 1.83E+09 3.01 E+07 7.93E+09 1.26E+09 6.80E+09 2.84E+04 0.00E+00 3.94E+03 2.00E+05 Lung 1.57E+03 0.OOE+00 8.58E+04 0.OOE+00 4.55E+07 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 1.58E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.12E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.0OE+00 2.85E+09 1.87E+08 2.45E+09 5.19E+04 0.0OE+00 0.OOE+00 0.OOE+00 GI-LLI 1.57E+03 1.82E+09 4.49E+06 1.24E+07 1.63E+08 2.24E+07 5.50E+07 1.63E+08 1.38E+09 1.66E+09 4.76E+08 2.05E+08 1.02E+09 4.11E+06 6.89E+05 1.88 E+08 6.94E-07 5.72E+07 1.25E+04 9.01E+04 1.01E+06 1.20E+10 0.00E+00 0.00E+00 1.27E+08 2.72E+08 9.92E+07 7.28E+06 1.38E+08 8.29E+07 1.31E+08 5.04E+0 7 1.61E+05

1. 12E+07 9.41 E+07 All nuclides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 108 of 133 ATTACHMENT J Page 15 of 19 P&I ORGAN DOSE FACTORS Table 2.3-16 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway= Cow Milk Age Group= Infant 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-1 10m Sb-124 Sb-I 25 Te-12 7m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 1.36E+11 0.OOE+00 0.OOE+00 1.81 E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.97E+09 1.97E+09 0.OOE+00 1.01E+10 8.22E+10 5.79E+04 5.33E+03 4.87E+05 2.63E-I1 0.OOE+00 2.34E+01 7.06E+03 1.34E+05 2.75E+08 0.OOE+00 0.OOE+00 3.16E+08 4.58E+08 2.31 E+09 3.08E+07 2.51E+10 1.68E+09 3.48E+10 2.05E+08 3.45E+01 3.57E+04 1.65E+06 Liver 2.38E+03 7.99E+09 0.OOE+00 2.76E+07 3.16E+08 6.36E+06 1.89E+07 6.OOE+07 1.3 6E+ 10 1.25E+09 1.88E+1 0 0.OOE+00 0.OOE+00 0.OOE+00 1.30E+03 2.0 IE+05 5.62E-12 1.77E+08 4.82E+0 I 0.OOE+00 0.OOE+00 2.01E+08 0.OOE+00 0.OOE+00 1.05E+08 1.57E+08 2.72E+09 4.49E+07 4.69E+10 4.93E+09 4.07E+10 2.05E+05 1.36E+01 2.18E+04 6.75E+05 T. Body 2.38E+03 5.27E+09 1.34 E+ 05 6.25E+ 06 1.25 E+ 08 1.03E+ 07 4.70E+ 07 1.42E+08 6.27E+09 2.47E+09 9.28E+09 2.89E+08 2.09E+ 10 1.54E+03 9.22E+02 1.16E+05 2.03E-12 3.45 E+ 07 6.21E+02 2.36E+ 03 1.67E+04 1.33E+08 0.OOE+00 0.00E+00 3.83E+ 07 7.06E+07 1.20E+09 1.31 E+ 07 4.73 E+ 09 1.84 E+ 09 2.89E+09 1.05 E+ 07 3.50E+00 2.57E+03 9.25E+04 Thyroid 2.3 8E+03 0.OOE+00 8.75E+04 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 1.07E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 9.14E+07 1.76E+08 8.95E+1 I 8.17E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 2.38E+03 0.OOE+00 1.91 E+04 6.11E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 6.60E+09 1.82E+09 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 1.40E+03 1.44E+05 4.39E-12 2.64 E+08 5.19E+02 1.47E+04 1.58E+05 2.88E+08 0.00E+00 0.00E+00 7.79E+08 1.15E+09 3.18E+09 5.28 E+07 1.21 E+I 0 1.97E+09 1.09E+1 0 4.86E+04 0.OOE+00 6.72 E+03 2.73E+05 Lung 2.38E+03 0.OOE+00 1.70E+05 0.OOE+00 9.35E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.58E+09 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 2.52E+01 0.0OE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.95E+09 4.02E+08 4.43E+09 1.26E+05 0.OOE+00 0.0OE+00 O.OOE+00 GI-LLI 2.38E+03 1.84E+09 3.91 E+06 1.01 E+07

1. 51 E+08

2. 17E+07 4.70E+07 1.43E+08 1.15E+10 1.66E+09 4.81E+08 2.07E+08 1.03E+09 4.15E+06 6.47E+05 1.69E+08

1. 77 E-06 5.83E+07 1.40E+04

8. 59E+04

1. 01 E+06 1.04E+I 0 0.00E+00 0.00E+00

1. 28 E+08 2.74E+08 9.72E+07 7.60E+06 1.27E+08 7.49E+07 1.27E+08 5.02E+07 1.60E+05

1. 13E+07 9.47E+07 All nuclides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 109 of 133 ATTACHMENT J Page 16 of 19 P&I ORGAN DOSE FACTORS Table 2.3-17 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrelr/r per uCi/sec)

Pathway = Goat Milk Age Group= Adult Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-1106 Ag-I10m, Sb-1 24 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 1.74E+10 O.OOE+00 0.OOE+00 3.12E+05 0.OOE+00 0.OOE+00 0.OOE+00 1.18E+08 2.22E+08 0.OOE+00 2.43E+09 6.64E+10 8.14E+02 8.87E+01 8.13E+03 3.38E-13 0.OOE+00 3.39E-01 9.95 E+01 1.72E+03 4.99E+06 0.OOE+00 0.00E+00 4.13 E+06 5.94E+06 3.02E+08 3.95E+06 4.67E+08 6.70E+08 1.50E+10 2.74E+06 4.60E-01 4.79E+02 3.05E+04 Liver 1.56E+03 1.08E+09 0.OOE+00 7.14E+05 7.32E+05 1.09E+05 4.40E+05 1.34E+06 3.74E+08 1.4 IE+08 2.63E+08 0.0OE+00 O.OOE+00 0.OOE+00 2.8 5E+0 1 4.5 2E+03 8.54E-14 2.53E+06 9.5 9E-0 I 0.OOE+00 0.OOE+00 4.6 IE+06 0.OOE+00 0.00E+00 1.48E+06 2.22E+06 4.32E+08 6.87E+06 1.1 IE+09 2.65E+09 2.0 5E+ 10 3.44E+03 2.32E-01 3.24E+02 1.27E+04 T. Body 1.56E+03 6.72E+08 2.85 E+ 03 1.36E+05 2.81E+05 1.82E+05 9.86E+05 2.96E+ 06 1.69E+08 2.78E+08 1.22 E+ 08 6.99E+07 1.63E+ 10 2.18E+01 1.93E+-01 2.43 E+ 03 3.12E-14 4.81E+05 1.22E+01 4.29E+01 2.18E+02 2.74 E+ 06 0.OOE+00 0.00E+00 5.03E+05 9.41 E+ 05 2.48E+08 2.09 E+ 06 9.09 E+ 08 1.90E+09 i.34E+ 10 1.79E+05 6.13E-02 3.68E+01 1.64 E+ 03 Thyroid 1.56E+03 0.OOE+00 1.70E+03 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.21E+08 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0GE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.05E+06 2.04E+06 1.42E+11 1.0 IE+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 1.56E+03 0.00E+00 6.28E+02 2.12E+05 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 2.50E+08 2.06 E+0 8 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 4.47E+01 4.47E+03 9.96E-14 5.72 E+0 6 1.46E+01 3.80E+02 3.32 E+03 9.07E+06 0.OOE+00 0.OOE+00 1.68E+07 2.48 E+0 7 7.40E+08 1.20E+07 3.60E+08 1.47E+09 6.95E+09 1.17E+03 0.00E+00 1.51 E+02 7.55 E+0 3 Lung 1.56E+03 0.OOE+00 3.78E+03 0.OOE+00 2.05E+05 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.78E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 4.70E-01 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

1. 19E+08 2.02E+08 2.3 1E+09 1.97E+03 0.OOE+00 0.00E+00 0.OOE+00 GI-LLI

1. 56 E+03 1.96E+09 7.17E+05

2. 19E+06 2.44E+06 2.77E+06 8.91E+06 2.52E+07

2. 36E+08

1. 87 E+08

5. 18E+07 3.91E+08 1.92E+09 4.48E+05 9.02E+04

2. 74E+07 3.15E-10 5.86E+06 5.67E+02

1. 16E+04 1.I1E+05

1. 88 E+09 0.OOE+00 0.00E+00

1. 38E+07

2. 99E+07

1. 14E+08 6.17E+06 1.95 E+07 3.01 E+08 3.96E+08 5.64E+06

1.

70 E+04 1.24E+06 1.03E+07 All nuclides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

110of133 ATTACHMENT J Page 17 of 19 P&I ORGAN DOSE FACTORS Table 2.3-18 R VALUES FOR BEAVER VALLEY SITE (sq meter-mremiy r per uCi/sec)

Pathway= Goat Milk Age Group= Teen 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-I 25 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-I 41 Ce-144 Bone 0.OOE+00 3.21E+10 0.OOE+00 O.OOE+00 5.44E+05 O.OOE+00 0.00E+00 O.OOE+00 1.81 E+08 2.86E+08 0.OOE+00 4.49E+09 9.39E+10 1.50E+03 1.55E+02 1.39E+04 6.15E-13 0.OOE+00 5.88E-01 1.77E+02 2.44E+03 8.24E+06 0.00E+00 0.00E+00 7.61 E+06 1.09E+07 5.48E+08 7.21E+06 8.11 E+08 1.14E+09 2.71E+10 4.94E+06 8.27E-01 8.79E+02 5.60E+04 Li ver 2.03E+03 1.99E+09 0.OOE+00 L.I 9E+06 1.27E+06 1.92E+05 7.40E+05 2.27E+06 6.27E+08 1.82E+08 4.79E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.90E+O 1 7.69E+03 1.53E-1 3 4.56E+06 1.64E+00 0.OOE+00 O.OOE+00 7.80E+06 0.OOE+00 0.OOE+00 2.70E+06 4.03E+06 7.67E+08 1.22E+07 1.91E+09 4.49E+09 3.61E+10 6.06E+03 4.06E-01 5.87E+02 2.32E+04 T. Body 2.03E+03 1.24E+09 4.98 E+ 03 2.36E+05 4.90 E+ 05 3.21 E+ 05 1.71 E+ 06 5.11 E+ 06 2.93 E+ 08 3.59E+08 2.25 E+ 08 1.29E+08 2.32E+ 10 4.01E+01 3.37E+01 4.23E+03 5.57E-14 8.70E+05 2.13E+ 01 7.56E+01 3.98E+ 02 4.75 E+ 06 0.00E+00 0.00E+ 00 9.05E+05 1.72E+ 06 4.12E+08 3.73 E+ 06 8.86E+08 3.02E+ 09 1.26E+ 10 3.18 E+ 05 1.08E-01 6.74E+01 3.01E+03 Thyroid 2.03E+03 0.OOE+00 2.77E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 1.56E+08 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.81E+06 3.5 1E+06 2.24E+1 1 1.7 IE+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 2.03 E+03 0.00E+00 1.09E+03 3.55E+05 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 4.01 E+08 2.65 E+0 8 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.19E+01 7.45E+03 1.79E-13 1.04E+07 2.45 E+01 6.24E+02

6. lOE+03 1.49E+07 0.00E+00 0.00E+00 3.08 E+07 4.55E+07 1.32E+09 2.15 E+07 6.07E+08 2.44E+09 1.23E+ 10 2.05 E+03 0.OOE+00 2.76E+02 1.39E+04 Lung 2.03E+03 0.OOE+00 7.1 IE+03 0.OOE+00 4.OOE+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.29E+08 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 9.1 IE-01 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 2.32E+08 3.85E+08 4.77E+09 4.07E+03 0.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 2.03E+03 2.70E+09 8.37E+05 2.44E+06 3.00E+06 3.57E+06

1. 02E+07 2.96E+07

2. 66E+08 2.41 E+08 7.09E+07 5.35E+08 2.64E+09 6.14E+05

1. 13E+05 3.29E+07 3.65E-09

8. 17E+06 1.08E+03 1.48E+04 1.52E+05 2.19E+09

0. OOE+00 0.00E+00

1. 90E+07 4.08E+07

1. 52E+08 9.26E+06 2.38E+07 3.61 E+08 5.14E+08 7.62 E+06 2.33E+04 1.68E+06 1.41 E+07 All nucides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 111 of 1-33 ATTACHMENT J Page 18 of 19 P&I ORGAN DOSE FACTORS Table 2.3-19 R VALUES FOR BEAVER VALLEY SITE (sq meter-mrem/yr per uCi/sec)

Pathway = Goat Milk Age Group = Child 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 Nuclide H-3 P-32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-1 10m Sb-1 24 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 7.91E+10 0.OOE+00 0.OOE+00 1.26E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.54E+08 2.36E+08 0.OOE+00 1.11E+10 1.59E+11 3.70E+03 3.60E+02 3.13E+04 1.49E-12 0.OOE+00 1.35E+00 4.18E+02 7.79E+03 1.79E+07 0.00E+00 0.OOE+00 1.88E+07 2.68E+07 1.33E+09 1.75E+07 1.87E+09 2.58E+09 6.54E+10 1.19E+07 1.98E+00 2.16E+03 1.38E+05 Liver 3.20E+03 3.70E+09 0.OOE+00 1.78E+06 2.04E+06 3.27E+05 1.13E+06 3.53E+06 9.44E+08 1.50E+08 8.88E+08 0.OOE+00 0.OOE+00 0.OOE+00 7.92E+01 1.22E+04 2.70E-13 8.30E+06 2.65E+00 0.OOE+00 O.OOE+00 1.2 IE+07 0.OOE+00 0.OOE+00 5.05E+06 7.48E+06 1.34E+09 2.17E+07 3.07E+09 7.08E+09 6.26E+1 0 1.05E+06 6.92E-01 1.08E+03 4.33E+04 T. Body 3.20E+03 3.05 E+ 09 1.02E+04 4.74E+05 1.02E+ 06 6.63 E+ 05 3.46E+ 06 1.04E+ 07 5.87 E+ 08 2.96 E+ 08 5.46 E+ 08 3.17E+08 4.02E+ 10 9.89E+01 7.05E+01 8.71E+03 1.26E-13 2.05 E+ 06 4.39E+01 1.61E+02 9.72E+02 9.65 E+ 06 0.00E+00 0.00E+00 2.23 E+ 06 4.16E+ 06 7.60 E+ 08 8.20E+06 6.48E+08 4.58E+09 9.24 E+ 09 6.96E+05 2.23E-01 1.60E+03 7.37E+03 Thyroid 3.20E+03 0.OOE+00 5.64E+03 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.29E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.48E+06 8.64E+06 4.42E+1 I 4.03E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 3.20E+03 0.00E+00 1.54E+03 4.99E+05 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 5.95 E+08 2.19E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.13 E+02 1.14E+04 2.99E-13 I.77E+07 3.84E+01 1.05E+03 1.05E+04 2.25E+07 0.00E+00 0.00E+00 5.35E+07 7.87 E+07 2.19E+09 3.61E+07 9.52E+08 3.77E+09 2.04E+ 10 3.40E+03 0.00E+00 4.73 E+02 2.40E+04 Lung 3.20E+03 0.OOE+00 1.03E+04 0.OOE+00 5.9 IE+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.89E+08 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 1.34E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.42E+08 5.62E+08 7.34E+09 6.23E+03 0.0OE+00 0.OOE+00 0.0OE+00 GI-LLI 3.20E+03 2.19E+09 5.39E+05

1. 49E+06 2.12E+06 2.68E+06

6. 60E+06 1.95E+07 1.66E+08 1.99E+08 5.71E+07 4.30E+08 2.14E+09 4.93E+05 8.27E+04 2.25 E+07 8.33E-08

6. 87E+06 1.51 E+03 1.08E+04 1.21 E+05 1.44E+09 0.OOE+00

0. OOE+00

1. 52 E+07 3.27E+07

1. 19E+08 8.73E+06 1.66E+07 2.49E+08 3.92E+08 6.04E+06 1.93 E+04 1.35E+06

1. 13E+07 All nucides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1_112_of 133 ATTACHMENT J Page 19 of 19 P&I ORGAN DOSE FACTORS 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 H-3 P -32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-I 10m Sb-124 Sb-125 Te-127m Te-129m 1-131 1-133 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Bone 0.OOE+00 1.63E+11 0.OOE+00 0.OOE+00 2.35E+06 0.OOE+00 0.OOE+00 0.OOE+00 4.76E+08 2.36E+08 0.00E+00 2.11E+10 1.73 E+1]

6.94E+03 6.40E+02 5.84E+04 3.16E-12 0.OOE+00 2.81 E+00 8.47E+02 1.60E+04 3.30E+07 0.00E+00 0.00 E+00 3.80E+07 5.50E+07 2.77E+09 3.70E+07 3.02E+09 5.03 E+09 1.04E+11 2.45 E +07 4.14E+00 4.29E+03 1.98E+05 Liver 4.86E+03 9.59E+09 0.00E+00 3.3 IE+06 4.1 IE+06 7.64E+05 2.26E+06 7.20E+06 1.63E+09 1.50E+08 2.25E+09 0.0OE+00 0.OOE+00 0.OOE+00 1.56E+02 2.4 IE+04 6.74E-13 2.12E+07 5.79E+00 0.OOE+00 0.OOE+00 2.4 1E+07 0.OOE+00 0.OOE+00 1.26E+07 1.89E+07 3.27E+09 5.39E+07 5.62E+09 1.4 8E+1 0 1.22E+1 I 2.45E +04 1.63E+00 2.62E+03 8.1 IE+04 T. Body 4.86 E+ 03 6.32 E+ 09 1.61E+04 7.50E+05 1.62 E+ 06 1.24E+06 5.64 E+ 06 1.70E+ 07 7.53 E+ 08 2.96 E+ 08 1.11 E+ 09 6.06 E+ 08 4.39E+ 10 1.85 E+ 02 1.11 E+ 02 1.39E+04 2.43 E-13 4.14 E+ 06 7.46 E+ 01 2.83 E+ 02 2.00 E+ 03 1.60E+ 07 0.00E+ 00 0.OOE+00 4.59 E+ 06 8.47 E+ 06 1.44 E+ 09 1.58E+07 5.68 E+ 08 5.52 E+ 09 8.66 E+ 09 1.26 E+ 06 4.19E-01 3.08 E+ 02 1.11 E+ 04 Thyroid 4.86E+03 0.OOE+00 1.05E+04 0.OOE+00 0.0OE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.00E-00 1.29E+08 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0CE+00 0.0OE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 I.IOE+07 2.1 IE+07 1.07E+12 9.80E+09 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.0OE+00 0.0CE+00 0.00E+00 Kidney 4.86E+03 0.OOE+00 2.29E+03 7.33 E+0 5 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 7.92E+08 2.19 E+0 8 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.68E+02 1.72E+04 5.27 E-13 3.17E+07 6.23 E+01 1.76E+03 1.90E+04 3.45 E+07 0.OOE+00 0.OOE+00 9.35E+07 1.38E+08 3.82E+09 6.34E+07 1.45 E+09 5.90E+09 3.28 E+ 10 5.83E+03 0.00E+00 8.07 E+02 3.28E+04 Lung 4.86E+03 0.OOE+00 2.04E+04 0.OOE+00 1.2 IE+06 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1.89E+08 0.OOE+00 0.0OE+00 0.0OE+00 0.00E +00 0.0OE+00 0.0OE+00 0.0OE+00 0.0CE+00 3.03E+00 0.0CE+00 0.OOE+00 O.OOE+00 0.0OE+00 0.0OE+00 0.0OE+00 0.00E+00 0.0OE+00 0.0OE+00 5.93E+08 1.2 IE+09 1.33E+10 1.5 1E+04 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI

4. 86E-03 2.21 E+09 4.69E+05

1. 21 E+06 1.96E+06 2.60E+06 5.64E+06 1.71E+07 1.38E+09 1.99E+08 5.77E+07 4.34E+08

2. 16E+09 4.98E+05 7.77 E+04 2.03 E+07

2. 13E-07 6.99E+06

1. 68 E+03 1.03 E+04 1.22E+05 1.25E+09

0. 00 E+00 0.OOE+00

1. 53 E+07 3.28E+07

1. 17E+08

9. 12E+06

1. 53 E+07 2.25E+08 3.82 E+08

6. 03E+06 1.92 E+04 1.35 E+06

1. 14E+07 All nuclides (except H-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCM equation 2.3-28

TABLE 2.3-21 PV-1/2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR

-2 (meters)

DISTANCES TO THE CONTROL LOCATIONS, IN MILES 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 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 6.OOE-10 6.66E-10 1.03E-09 1.13E-09 1.35E-09 9.82E-10 2.76E-09 2.22E-09 3.OOE-09 1.44E-08 1.89E-08 1.57E-09 3.78E-10 4.54E-10 4.52E-10 3.40E-10 8.60E-09 5.64E-09 1.57E-09 1.55E-09 1.28E-08 7.85E-09 6.41E-09 4.66E-09 4.81E-09 2.89E-09 5.55E-09 6.63E-09 2.95E-09 4.13E-10 4.09E-10 2.05E-09 3.14E-09 1.98E-09 1.32E-09 3.69E-09 4.09E-09 4.40E-09 3.52E-09 3.01E-09 3.76E-09 7.83E-10 1.55E-09 1.36E-09 1.84E-09 3.09E-10 2.86E-10 1.63E-09 1.76E-09 2.55E-09 3.62E-09 3.27E-09 3.12E-09 2.46E-09 1.97E-09 1.68E-09

2. 1OE-09 8.84E-10 8.71E-10 1.04E-09 1.03E-09 4.71E-10 1.18E-09 9.12E-10 8.12E-10 1.33E-09 2.63E-09 2.3 1E-09 1.91 E-09 1.47E-09 1.18E-09 1.02E-09 1.36E-09 5.70E-10 2.61E-10 5.44E-10 6.63E-10 7.35E-10 7.04E-10 5.86E-10 5.70E-10 1.07E-09 1.64E-09 1.29E-09 1.36E-09 1.03E-09 8.27E-10 7.14E-10 9.52E-10 4.OOE-10 3.94E-10 2.39E-10 4.66E-10 5.16E-10 4.94E-10 4.13E-10 4.24E-10 6.75E-10 1.23E-09 1.21E-09 1.01E-09 5.65E-10 5.68E-10 4.25E-10 5.12E-10 2.55E-10 1.57E-10 3.84E-10 1.37E-10 1.93E-10 3.37E-10 2.79E-10 3.29E-10 5.23E-10 6.13E-10 6.78E-10 7.83E-10 5.05E-10 4.40E-10 3.29E-10 3.96E-10 1.98E-10 2.50E-10 2.98E-10 2.68E-10 1.IOE-10 2.10E-10 2.16E-10 2.63E-10 4.56E-10 7.85E-10 6.72E-10 4.15E-10 3.25E-10 2.93E-10 2.19E-10 2.68E-10 1.84E-10 2.54E-10 2.17E-10 1.12E-10 1.12E-10 2.09E-10 1.73E-10 2.15E-10 3.74E-10 6.42E-10 3.89E-10 5.10E-10 3.OOE-10 2.43E-10 1.80E-10 2.20E-10 1.51E-10 2.08E-10 1.78E-10 1.75E-10 1.80E-10 1.71E-10 1.42E-10 cnT 0

tll-HH C~~)

H 0

ti-I 0

ti-I w

(D 0D

(

C-.

C, C,

~-

C~

-C)

C, 0

C, zO I-a-I.-

Y TABLE 2.3-22 CV-I AND CV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR

-2 (meters DISTANCES TO THE 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 4.0-4.5 4.5 - 5.0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 4.46E-08 5.42E-08 7.32E-08 7.77E-08 6.08E-08 3.23E-08 3.29E-08 2.84E-08 3.67E-08 2.61E-08 3.06E-08 4.60E-08 6.49E-08 9.25E-08 1.19E-07 5.22E-08 7.73E-09 9.39E-09 1.27E-08 1.35E-08 1.05E-08 5.60E-09 5.70E-09 4.92E-09 6.37E-09 4.52E-09 5.30E-09 7.97E-09

1. 13E-08 1.60E-08 2.07E-08 9.04E-09 3.24E-09 3.37E-09 6.21E-09 6.5 1E-09 3.79E-09 2.54E-09 2.59E-09 2.06E-09 2.26E-09 1.60E-09 2.62E-09 3.34E-09 4.72E-09 6.43E-09 8.68E-09 3.79E-09 1.81E-09 1.89E-09 3.47E-09 3.64E-09 2.12E-09 1.42E-09 1.45E-09

1. 15E-09 1.26E-09 8.97E-10 1.47E-09 1.87E-09 2.64E-09 3.60E-09 4.86E-09 2.12E-09 1.08E-09 1.22E-09 2.24E-09 2.50E-09 1.37E-09 8.46E-10 9.32E-10 6.29E-10 8.14E-10 5.78E-10 8.01E-10 1.20E-09 1.19E-09 2.21E-09 2.99E-09 1.28E-09 7.57E-10 8.54E-10 1.57E-09 1.76E-09 9.59E-10 5.94E-10 6.55E-10 4.42E-10 5.71E-10 4.06E-10 5.62E-10 8.45E-10 8.36E-10 1.55E-09 2.1OE-09 9.OOE-10 5.16E-10 6.35E-10 1.001E-09 1.3 1E-09 6.54E-10 4.05E-10 4.12E-10 2.99E-10 3.86E-10 3.02E-10 4.18E-10 5.87E-10 6.22E-10

1. 16E-09 1.56E-09 6.25E-10 4.00E-10 4.92E-10 7.77E-10 1.0 1E-09 5.06E-10 3.14E-10 3.19E-10 2.32E-10 2.99E-10 2.34E-10 3.24E-10 4.55E-10 4.82E-10 8.96E-10 1.21E-09 4.84E-10 2.91E-10 3.94E-10 5.69E-10 6.5 8E-10 4.05E-10 2.28E-10 2.55E-10 1.85E-10 2.39E-10 1.70E-10 2.35E-10 3.38E-10 3.85E-10 5.79E-10 7.83E-10 3.59E-10 2.388E-10 3.22E-10 4.66E-10 5.3 9E-10 3.32E-10 1.87E-10 2.09E-10 1.52E-10 1.96E-10 1.39E-10 1.93E-10 2.77E-10 3.15E-10 4.75E-10 6.41E-10 2.94E-10 00 0

tIw 0

trl H.

H-.

C-)

c/)

0 ti-i c/)

L.j go 0

C 0

0 0

C,-D 0

0 0

C-)

N)

CDC 0

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 115 of 133 ATTACHMENT K Page 3 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)

TABLE 2.3-23 VV-1 AND VV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters"2)

Same as Table 2.3-22

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 116 of 133 ATTACHMENT K Page 4 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)

TABLE 2.3-24 TV-2 DEPOSITION 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:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 1_117 of 133 ATTACHMENT K Page 5 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)

TABLE 2.3-25 CB-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters"2)

Same as Table 2.3-22

Procedure Number:

Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 118 of 133 ATTACHMENT K Page 6 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)

TABLE 2.3-26 DV-2 DEPOSITION 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:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

119 of 133 ATTACHMENT K Page 7 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)

TABLE 2.3-27 WV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters"2)

Same as Table 2.3-22

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 120 of 133 ATTACHMENT L Page 1 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-28 PV-1/2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(I E-9 meters-2)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW

.600

.673

.766 1.010 1.370

.984 11.000 7.060 5.780 2.040 1.610 1.710

.377

.424

.447 2.340 3.220 1.280 5.080 4.420 6.390 3.680 3.220 1.540 1.040 1.120 1.310

.659

.746

.425

.660

.401

.466

.423 1.410

.578

.370

.138

.497

.572

.524

.111

.702 1.290 2.340

.466

.105

.208

.693

.029

.070

.707 2.920

.660 1.290 6.390 1.300 3.140 2.610 1.040

.979 1.190

.518

.746

.488 2.510 3.220 1.200 1.760 4.420 6.180 3.680 4.320 2.730 1.460 1.120 1.310

.659

.746

.422 NNW

.340 1.840

.043

.545 1.92

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

121 of 133 ATTACHMENT L Page 2 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-29 CV-1 AND CV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRS/YR OR > 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(1E-9 meters-2 )

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 25.40 18.80 63.40 65.90 38.00 17.10 13.80 10.50 10.60 5.59 3.94 27.50 31.60 39.10 70.60 31.50 2.05 2.02 29.30 8.92 3.90 3.56 3.03 2.65 1.05 1.26 2.21 2.65 1.23 2.23 15.00 6.52

.455

.382

.350

.317

.934

.663

.596

.645 1.490

.693

.459

.078

.661 1.020 1.380

.350

.094

.266 1.320

.045

.276

.068

.847 1.850

.455 1.020 3.560 1.100 2.570 1.860 1.260 1.920 2.380

.960 2.230 1.990 1.090 2.19 2.11 30.40 32.20 22.70 3.56 3.03 3.68 1.95 4.42 2.21 2.65 1.23 2.23 15.60 9.91

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3 1

122 of 133 ATTACHMENT L Page 3 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-30 VV-I AND VV-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)

(I E-9 meters"2)

Same as Table 2.3-29

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 123 of 133 ATTACHMENT L Page 4 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-31 TV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(I E-9 meters"2)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 20.20 34.90 54.20 57.50 38.10 18.60 19.00 13.30 11.30 6.44 3.95 25.10 28.40 30.90 56.10 25.10 2.05 2.02 29.30 8.92 3.90 3.56 3.03 2.65 10.40 1.26 2.21 2.65 1.23 2.23 14.90 6.53

.455

.382

.351

.318

.934

.664

.597

.646 1.490

.693

.459

.078

.661 1.020 1.380

.351

.094

.266 1.320

.045

.276

.068

.847 1.850

.455 1.020 3.560 1.100 2.570 1.860 1.260 1.920 2.380

.961 2.230 1.980 1.100 2.190 2.110 30.400 32.200 22.700 3.560 3.030 3.690 1.950 4.430 2.210 2.650 1.230 2.230 15.500 9.920

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 124 of 133 ATTACHMENT L Page 5 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-32 CB-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(1 E-9 meters-)

Same as Table 2.3-31

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

125 of 133 ATTACHMENT L Page 6 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-33 DV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES

>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(1E-9 meters-2 )

Same as Table 2.3-29

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

126 of 133 ATTACHMENT L Page 7 of 7 CONTINUOUS RELEASE DEPOSITION 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)

(1E-9 meters-2)

Same as Table 2.3-29

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

3 127of133 ATTACHMENT M Page 1 of3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-35 CV-1 AND CV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES

>500 HRS/YR OR >_150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(sec/mr3)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*

BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 8.21E-5 3.04E-5 4.59E-5 3.72E-5 2.93E-5 2.47E-5 2.14E-5 2.21E-5 2.15E-5 2.18E-5 1.82E-5 1.09E-4 1.49E-4 1.91E-4 3.08E-4 1.80E-4 8.38E-6 4.71E-6 2.21E-5 5.25E-6 3.79E-6 5.61E-6 5.OOE-6 6.3 1E-6 3.03E-6 6.58E-6 1.03E-5 1.29E-5 1.05E-5 1.72E-5 6.13E-5 3.54E-5 3.72E-6 1.40E-6 6.05E-7 1.38E-7 5.66E-7 5.15E-7 8.13E-7

1. 1 E-6 2.76E-6 3.8 1E-6 4.1OE-6 1.17E-6 2.34E-6 8.13E-7 3.92E-7 1.82E-6 6.67E-6 4.34E-6 4.38E-6 6.05E-7 1.1 7E-6 5.61 E-6 2.03E-6 6.13E-6 4.93E-6 6.58E-6 9.12E-6 1.19E-5 8.77E-6 1.72E-5 1.36E-5 9.27E-6 8.82E-6 4.87E-6 2.28E-5 1.88E-5 1.78E-5 5.6 1E-6 5.OOE-6 8.49E-6 5.14E-6 1.78E-5 1.03E-5 1.29E-5 1.05E-5 1.72E-5 6.36E-5 5.29E-5 6.55E-6 1.28E-5 1.23E-6 3.80E-6 1.35E-6

Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 128 of 133 ATTACHMENT M Page 2 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-36 VV-1 AND VV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES

>500 HRS/YR OR Ž 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(sec/mr3)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*

BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 9.75bE-5 3.78E-5 6.13E-5 4.83E-5 3.66E-5 2.99E-5 2.55E-5 2.65E-5 2.52E-5 2.60E-5 2.13E-5 1.34E-4 1.77E-4 2.33E-4 3.32E-4 1.90E-4 1.ULE-5 5.11 E-6 2.70E-5 5.58E-6 3.99E-6 6.13E-6 5.29E-6 6.72E-6 3.14E-6 7.34E-6 1.18E-5 1.51E-5 1.25E-5 2.07E-5 8.57E-5 4.69E-5 6.20E-7 5.25E-7 8.24E-7 1.12E-6 2.83E-6 4.15E-6 4.46E-6 7.40E-6 1.49E-5 4.21E-6 1.43E-6 1.40E-7 5.71E-7

1. 19E-6 2.43E-6 8.24E-7 3.95E-7 1.92E-6 7.41 E-6 1.30E-6 4.24E-6 1.45E-6 4.95E-6 4.72E-6 6.20E-7 1.19E-6 6.13E-6 2.13E-6 6.53E-6 5.29E-6 7.34E-6 1.04E-5 1.38E-5 1.02E-5 2.07E-5 1.64E-5 1.09E-5 1.06E-5 5.30E-6 2.8 1E-5 2.24E-5 2.1OE-5 6.13E-6 5.29E-6 9.22E-6 5.53E-6 2.09E-5 1.18E-5 1.51E-5 1.25E-5 2.07E-5 8.85E-5 6.75E-5

Measured relevant to center point between BV-I and BV-2 Containment Buildings Period of Record: 1976 - 1980

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1_3 129 of 133 ATTACHMENT M Page 3 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)

TABLE 2.3-37 PV-1/2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES

>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)

(sec/mr3)

INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR*

BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 3.09E-9 2.85E-9 2.02E-10 1.02E-9 2.15E-9 6.90E-9 2.91 E-6 4.9 1E-6 2.41 E-6 4.83E-6 4.82E-6 5.77E-7 2.88E-9 3.40E-9 1.34E-9 1.52E-9 3.30E-6 2.68E-6 7.42E-9 3.2 1E-6 2.9 1E-6 4.97E-6 3.52E-6 3.56E-6 1.78E-6 2.52E-6 2.75E-6 2.8 1E-6 1.68E-6 1.61E-6 3.3 1E-8 3.73E-6 1.13E-6 6.52E-7 5.44E-7 1.24E-7 6.29E-7 4.96E-7 6.02E-7 6.53E-7 1.65E-6 1.50E-6 8.79E-7 1.14E-6 1.95E-6 6.02E-7 2.18E-7 6.60E-7 1.78E-6 1.34E-6 2.47E-6 5.44E-7 1.14E-6 4.97E-6 1.43E-6 3.47E-6 2.84E-6 2.52E-6 2.44E-6 2.57E-6 1.37E-6 1.61E-6 1.07E-6 1.31E-6 3.36E-6 2.68E-6 5.5 1E-9 1.67E-9 2.91E-6 4.8 1E-6 3.52E-6 4.71E-6 2.96E-6 3.96E-6 2.75E-6 2.81 E-6 1.68E-6 1.61E-6 3.1OE-8 3.81 E-6 4.89E-7 1.13E-6

1. 1OE-7 2.03E-7 1.73E-7

Measured relevant to BV-I natural draft cooling tower Period of Record: 1976 - 1980

TABLE 2.3-38 5

PV-1/2 DISPERSION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR Ž150 HRS/QTR (sec/rn 3) c/)

o DISTANCES TO THE CONTROL LOCATIONS, IN MILES m

CD 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 N

2.75E-15 1.07E-5 4.10E-6 2.61E-6 1.51E-6 1.13E-6 8.84E-7 7.13E-7 5.93E-7 5.06E-7 a

Z 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 5.64E-7 4.81E-7 r.

NE 4.45E-16 1.67E-8 7.39E-8 2.28E-6 1.72E-6 1.19E-6 9.28E-7 6.76E-7 7.34E-7 5.32E-7 C')

ENE 1.92E-15 8.87E-8 2.60E-6 2.21E-6 1.66E-6 1.13E-6 9.25E-7 7.23E-7 6.06E-7 3.82E-7 on E

1.84E-15 5.1OE-6 2.77E-6 2.23E-6 1.44E-6 1.12E-6 8.74E-7 6.92E-7 5.11E-7 4.82E-7

-q ESE 2.96E-13 5.26E-6 3.48E-6 2.04E-6 1.34E-6 9.93E-7 6.70E-7 5.76E-7 4.37E-7 3.83E-7

>')

SE 9.16E-8 3.13E-6 3.38E-6 1.99E-6 1.31E-6 9.58E-7 7.14E-7 5.74E-7 4.32E-7 3.68E-7 0

CD z -

SSE 3.50E-8 4.86E-6 3.33E-6 1.95E-6 1.29E-6 9.42E-7 6.55E-7 5.24E-7 3.95E-7 3.32E-7 S

1.22E-7 4.12E-6 3.97E-6 2.34E-6 1.59E-6 1.17E-6 7.75E-7 6.24E-7 4.74E-7 4.OOE-7 H

SSW 1.75E-5 6.22E-6 2.84E-6 2.18E-6 1.48E-6 1.08E-6 7.83E-7 6.31E-7 5.62E-7 4.77E-7 Z

SW 2.08E-5 9.11E-6 3.47E-6 2.19E-6 1.25E-6 1.1IE-6 8.19E-7 7.17E-7 6.89E-7 5.85E-7 WSW 8.56E-8 9.35E-6 3.16E-6 2.29E-6 1.46E-6 1.OIE-6 9.06E-7 7.52E-7 5.99E-7 5.07E-7 (n2 W5.44E-17 4.52E-6 4.21E-6 2.49E-6 1.69E-6 1.25E-6 4.86E-7 7.68E-7 5.80E-7 5.48E-7 WNW 9.25E-18 1.44E-8 5.66E-8 1.92E-6 1.59E-6

1. 17E-6 7.75E-7 4.6 1E-7 5.28E-7 4.89E-7 IQ NW 2.61E-16 1.98E-8 8.37E-8 2.24E-6 1.46E-6 1.08E-6 8.09E-7 6.12E-7 5.42E-7 4.60E-7 NNW 1.91E-15 3.91E-6 3.66E-6 2.15E-6 1.40E-6 1.08E-6 8.03E-7 6.48E-7 5.37E-7 4.56E-7 T

00 zt N82EEED WEEEE-4 t,- C~'~

CD-r on(

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

__3

- 1 131 of 133 ATTACHMENT 0 Page 1 of 1 GASEOUS RADWASTE SYSTEM FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADWASTE SYSTEM

Procedure Number:

Beaver Valley Power Station 1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3 1

132 of 133 ATTACHMENT P Page 1 of I BV-I AND BV-2 GASEOUS EFFLUENT RELEASE POINTS FIGURE 2.4-2 BV-i AND 2 GASEOUS EFFLUENT RELEASE POINTS Ohio Itver Note: The Release Point shown for the Unit 2 TurbIne BuildIng Vent Is a representt ive exhoust point for the 10 roof exhaust outlets.

Beaver Valley Power Station Procedure Number:

1/2-ODC-2.02

Title:

Unit:

Level Of Use:

1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:

Page Number:

1 3

1 133 of 133 ATTACHMENT Q Page 1 of I SITE BOUNDARY FOR GASEOUS EFFLUENTS Fieure 5-1

ML13126A045

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