ML13126A044

RTL A9.621B, Procedure 1/2-ODC-2.01, Rev. 12, ODCM: Liquid Effluents

ML13126A044
Person / Time
Site:	Beaver Valley
Issue date:	07/26/2012
From:	FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
L-13-129 1/2-ODC-2.01, Rev. 12, RTL A9.621B
Download: ML13126A044 (40)

Text

RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.01 ODCM: LIQUID EFFLUENTS Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 12 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 07/26/12 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 2 of 40 TABLE OF CONTENTS 1.0 P U R P O S E .........................................................................................................................................

3 2 .0 S C O P E ..............................................................................................................................................

3

3.0 REFERENCES

AND COMMITMENTS

...................................................................................

3 3 .1 R eferen ces ..............................................................................................................................

3 3 .2 C om m itm ents .........................................................................................................................

6 4.0 RECORDS AND FORMS ............................................................................................................

7 4 .1 R ecords ...................................................................................................................................

7 4 .2 F o rm ss ......................................................................................................................................

7 5.0 PRECAUTIONS AND LIMITATIONS

......................................................................................

7 6.0 ACCEPTANCE CRITERIA ........................................................................................................

7 7.0 P R E R E Q U ISIT E S ............................................................................................................................

8 8 .0 P R O C E D U R E ...................................................................................................................................

8 8 .1 A larm S etp oints ......................................................................................................................

8 8.1.1 BV- I Monitor Alarm Setpoint Determination

...................................................

8 8.1.2 BV-2 Monitor Alarm Setpoint Determination

.................................................

14 8.2 Compliance With 10 CFR 20 EC Limits (ODCM CONTROL 3.11.1.1)

........................

20 8.2.1 B atch R eleases ................................................................................................

20 8.2.2 Continuous Releases ........................................................................................

22 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.1.2 And 3.11.1.3).

22 8.3.1 Cumulation Of Doses (ODCM CONTROL 3.11.1.2)

....................................

22 8.3.2 Projection Of Doses (ODCM CONTROL 3.11.1.3)

.......................................

24 8.4 Liquid Radwaste System ................................................................................................

25 8.4.1 BV-1 Liquid Radwaste System Components

.................................................

25 8.4.2 BV-1 Laundry and Contaminated Shower Drain System Components

...... 27 8.4.3 BV-2 Liquid Radwaste System Components

................................................

28 ATTACHMENT A LIQUID SOURCE TERMS ...........................................................................

30 ATTACHMENT B INGESTION DOSE COMMITMENT FACTORS .......................................

34 ATTACHMENT C LIQUID RADWASTE SYSTEM ....................................................................

37 ATTACHMENT D SITE BOUNDARY FOR LIQUID EFFLUENTS

..........................................

40 Beaver Valley Power Station Procdure Nuo7DC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 1- 3 of 40 1.0 PURPOSE 1.1 This procedure provides the calculational methodology to be used for determination of the following release parameters as denoted in Unit 1/2 Technical Specifications ITS 5.5.2.(32l)

1.1.1 Liquid

effluent monitor alarm setpoints (ITS 5.5.2.a)1.1.2 Liquid effluent release concentration calculations (ITS. 5.5.2.b)1.1.3 Liquid effluent dose projection and cumulative dose calculations (ITS 5.5.2.d and ITS 5.5.2.e)1.2 This procedure also provides information related to the following:

1.2.1 Liquid

Radwaste Treatment System ITS 5.5.2.)1.2.2 Site Boundary used for liquid effluents 1.3 Prior to issuance of this procedure, these items were contained in Section 1 of the old ODCM.2.0 SCOPE 2.1 This procedure is applicable to all station personnel 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 Liquid 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, Appendix I Analysis -Docket No. 50-334 and 50-412; Table 2.1-2 3.1.1.3 10 CFR 20, Appendix B, (20.1001-20.2402)

Table 2, Column 2 EC's 3.1.1.4 Calculation Package No. ERS-SFL-92-039, Isotopic Efficiencies For Unit 1 Liquid Process Monitors 3.1.1.5 Calculation Package No. ERS-ATL-93-021, Process Alarm Setpoints For Liquid Effluent Monitors 3.1.1.6 Stone and Webster Calculation Package No. UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations

-Expect and Design Cases (per Unit and Site)

Beaver Valley Power Station Procedure NubrDC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 4 of 40 3.1.2 References for BV-2 Liquid Effluent Monitor Setpoints 3.1.2.1 10 CFR 20, Appendix B, (20.1001-20.2402)

Table 2, Column 2 EC's 3.1.2.2 Calculation Package No. ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies 3.1.2.3 Stone and Webster Computer Code LIQ1BB; "Normal Liquid Releases From A Pressurized Water Reactor" 3.1.2.4 Calculation Package No. ERS-JWW-87-015, Isotopic Efficiencies For 2SGC-RQ100 3.1.2.4.1 The Isotopic Efficiencies for 2SGC-RQ100 are superseded by the values presented in Calculation Package No. ERS-SFL-86-026.

3.1.2.5 Calculation Package No. ERS-WFW-87-021, Conversion Factor for 2SGC-RQ100 3.1.2.5.1 The Monitor Conversion Factor (CF 1 I) for 2SGC-RQ100 is superseded by the value presented in Calculation Package No. ERS-ATL-93-021.

3.1.2.6 Calculation Package No. ERS-ATL-93-021, Process Alarm Setpoints For Liquid Effluent Monitors 3.1.2.7 Stone and Webster Calculation Package No. UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations

-Expect and Design Cases (per Unit and Site)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-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWRs, Revision 0 3.1.3.4 Regulatory Guide 1. 113; Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977 3.1.3.5 Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance to 10 CFR Part 50, Appendix I 3.1.3.6 Calculation Package No. ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for HPM-RP 6.5, Issue 3 and Later Beaver Valley Power Station Procedure N1r:ODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 5 of 40 3.1.3.7 NUREG-0172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake 3.1.3.8 UCRL-50564; Concentration Factors of Chemical Elements in Edible Aquatic Organisms, Revision 1, 1972 3.1.3.9 l/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.3.10 1/2-ADM-0100, Procedure Writers Guide 3.1.3.11 NOP-SS-3001, Procedure Review and Approval 3.1.3.12 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3.13 CR 02-06174, Tracking of Activities for Unit 1 RCS Zinc Addition Implementation.

CA-014, Revise ODCM Procedure 1/2-ODC-2.01 (Tables 1.1-la and ib) to include the addition of Zn-65 to the ODCM liquid source term.3.1.3.14 CR 03-02466, RFA-Radiation Protection Effluent Control Provide Recommendation on Processing when Performing Weekly Sample of[1LW-TK-7A17B].

CA-02, Revise ODCM Procedure 1/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit 1 and Unit 2.3.1.3.15 CR 05-03306, Incorporated Improved Technical Specifications (ITS).3.1.3.16 CR 05-03854, ODCM Figure for Liquid Effluent Release Points Need Updated.CA-01, revise ODCM procedure 1/2-ODC-2.01 (ODCM: Liquid Effluents)

Attachment D, Figure 1.4-3 to incorporate a modified version of Plant Drawing No. 8700-RM-27F.

3.1.3.17 Unit 1 Technical Specification Amendment No. 275 (LAR 1A-302) to License No. DPR-66. This amendment to the Unit I license was approved by the NRC on July 19, 2006.3.1.3.18 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 1.3.1.3.19 Engineering Change Package No. ECP-04-0440, Extended Power Uprate.3.1.3.20 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies.

CA-03; revise ODCM procedure 1/2-ODC-2.01 to update the alarm setpoints of [RM-1RW-100]

and [RM-1DA-100]

for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275.

Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 6 of 40 3.1.3.21 CR 06-6476, Procedure 1/2-ODC-2.01 needs revised for Plant Uprate. CA-01;revise ODCM procedure 1/2-ODC-2.01 to update the alarm setpoints of[2SWS-RQ1O1]

for incorporation of the Extended Power Update at Unit 2 (ECP-04-0441) per Unit 2 TS Amendment No. 156.3.1.3.22 CR 05-00004-15, CR05-00004-17 and SAP Order 200197646-0010 to revise 1/2-ODC-2.01.

Add the Coolant Recovery Tanks [lBR-TK-4A/4B]

as Liquid Waste Tanks to Section 8.4 description and Attachment D Figures 1.4-1 and 1.4-2.Add a default 2-tank volume recirculation time of 45.7 hrs for the Coolant Recovery Tanks [1BR-TK-4A/4B]

to Attachment B Table 1.2-1a. Add the Cesium Removal Ion Exchangers

[1BR-I-1A/1B and 2BRS-IOE21A/21B) to Section 8.4 description and Attachment B Figures 1.4-1 and 1.4-2. Revise the recirculation times in Attachment B Table 1.2-1a and 1.2-1b to indicate the times for nominal tank volume and maximum tank volume.3.1.3.23 SAP Order 200197646-0660.

Revise 1/2-ODC-2.01 Attachment D Figure 1.4-3 to remove STP Outfalls 113 and 203 due to retirement of the Sewage Treatment Plants and to remove Ul Steam Generator Blowdown Filter Backwash Outfall 501. Water is no longer discharged via these outfalls.3.1.3.24 SAP Order 200197646-0810.

Revise 1/2-ODC-2.01 to incorporate alarm setpoints for all possible detector combinations for [RM- 1DA- 100]. Specifically, due to obsolescence of the original Model 843-30 and 843-32 detectors that were previously installed in [RM- IDA- 100], the vendor has upgraded them to Model 843-30R and 843-32R detectors, which include upgraded efficiency data as well.3.1.3.25 CR 10-86844 revises 1/2-ODC-2.01 to remove description that batch releases of liquid waste are processed by recirculation through eductors.

Deleted Attachment B which referenced minimum liquid waste batch release recirculation times and added description that liquid waste recirculation times to achieve two tank volumes are calculated based upon actual tank volume and pump capacity.3.1.3.26 ECP 11-0049 and CR 2012-02583 implement changes to the design of the liquid waste system for Phase 2 of Coolant Recovery Project.3.1.3.27 SAP Notification 600747531, Update 1/2-ODC-2.01 for RM-1RW-100.

3.1.3.28 CR-2012-05875, Antimony-126 identified in the liquid waste system.3.1.3.29 SAP Notification 600765150, Request from Operations to allow discharge of water in high level drains tanks [LW-TK-2A/B]

through low level waste tanks[LW-TK-3A/B]

via RM-LW-104.

3.2 Commitments

3.2.1 Unit 1 and 2 Technical Specifications:

ITS 5.5.2, Radioactive Effluent Controls Program Beaver Valley Power Station Procedure Number:____ ____ ___ ____ ___ ____ ____ ___ ____ __1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 7 of 40 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 BV-1 and BV-2 utilize the concept of a shared liquid radioactive waste system according to NUREG-0133.1 3'3') This permits the mixing of liquid radwaste for processing and allocating of dose due to release as defined in Section 8.4.5.1.1 In Section 8.1 of this procedure, effluent monitor setpoints for a conservative mix are based on the individual Units' specific parameters, but effluent monitor setpoints for analysis prior to release permit use of the total dilution flow available at the site.5.2 There is a difference in alarm setpoint terminology presentations for the radiation monitoring systems of BV-1 and BV-2.5.2.1 Where HIGH and HIGH-HIGH terminology are used for BV-1 monitors, Alert and High terminology is used for BV-2 monitors.5.2.2 BV-2 setpoints are presented in uCi/mi rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to the raw data (cpm). Note that the uCi/ml presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factors. Therefore, BV-2 setpoints determined on analysis prior to release will be correct for properly controlling dose rate, but the indicated uCi/ml value may differ from the actual value.5.3 This procedure also contains information that was previously contained in Section 5 of the previous BV-l and 2 Offsite Dose Calculation Manual.5.3.1 In regards to this, the site boundary for liquid effluents was included in this procedure.

5.3.2 The Site Boundary for Liquid Effluents is shown in ATTACHMENT D 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 or reliability of effluent dose or alarm setpoint calculation.(3 1 3 2)

I VProcedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 8 of 40 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100"O-1.3.) and 1/2-ADM-1640.23.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-300 1(31-.3-1 and l/2-ADM- 1640.3'-39'

7.0 PREREQUISITES

7.1 The user of this procedure shall be familiar with ODCM structure and format.8.0 PROCEDURE 8.1 Alarm Setpoints 8.1.1 BV-1 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIGH Alarm Setpoint (HHSP) that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the ECs specified in 10 CFR 20, Appendix B (20.1001-20.2402), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases. (3.1.1.5)The methodology described in Section 8.1.1.2 is an alternative method to be used to determine the [RM-1LW-104]

or [RM-lLW-1 16] monitor HHSP. The methodology in Section 8.1.1.2 may be used for any batch release and shall be used when the respective total gamma activity concentration of the liquid effluent prior to dilution exceeds 3.14E-3 uCi/mI and 7.33E-3 uCi/ml. This concentration is equivalent to the respective HHSPs derived in Section 8.1.1.1 and allows for respective tritium concentrations up to 4.26E+0 uCi/ml and 9.94E+O uCi/ml.(3 1 1 5 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: e Of Use: 1/2 Genera] Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 9 of 40 8.1.1.1 BV-1 Setpoint Determination Based On A Conservative Mix The Alarm Setpoints shall be set at the values listed in the following table: BV-i LIQUID MONITOR SETPOINTS cpm Above Background Monitor CR HHSP HSP Liquid Waste Effluent Monitor RM-ILW-104 3.53E+5 < 3.53E+5 2.47E+5 Laundry And Contaminated RM-lLW-116 8.24E+5 < 8.24E+5 < 5.77E+5 Shower Drains Monitor Component Cooling/ RM-1RW-100 2.57E+4 < 1.90E+4 < 1.33E+4 Recirculation Spray Hx River (3) (3)Water Monitor Component Cooling Hx River RM-IRW-101 9.02E+3 < 9.02E+3 < 6.32E+3 Water Monitor Aux Feed Pump Bay Drain RM-1DA-100 " (1 (1 Monitor with Detector 1.22E+4 < 1.20E+4 < 8.43E+3 Model 843-30 or (2) (2)843-32 1.05E+4 < 1.05E+4 < 7.33E+3 RM-IDA-100

1) ) (1)with Detector 1.22E+4 < 1.20E+4 < 8.43E+3 (2) (2) (2)Model 843-30R or 843-32R 1.22E+4 1 1.22E+4 < 8.52E+3 () Use these values for a monitor with an analog drawer/meter face. These values are from Calculation No.8700-UR(B)-223, and are justified for use in Attachment 6 of Calculation Package ERS-ATL-93-021.

(3.1.5)(3.1.3.1) 8 (2) Use these values when the monitor is upgraded to a digital drawer/meter face. These values are justified for use in Attachment 6 of Calculation Package ERS-ATL-93-02 1(3-.i.1 5)(3) Calculation Package ERS-ATL-93-021 Revision 4(3115)The setpoint bases for all monitors can be found in Calculation Package ERS-ATL-93-021 and/or Calculation No. 8700-UR(B)-223

.(3 1.3.1 ' The setpoints for RM- I LW- 104 and RM- I LW- 116 are based on the following conditions:

• Source terms given in ATTACHMENT A Table 1.1-la. These source terms (without Zn-65) have been generated from the GALE Computer Code, as described in NUREG-0017.(3 1 3 3) The inputs to GALE are given in 1/2-ODC-3.01 Appendix B. The Zn-65 source term was generated via Calculation Package No.ERS-ATL-93-021

.(3.1.1.5, 3.1.3.13)* Dilution water flow rate of 22,800 gpm = (15,000 gpm BV-I + 7,800 gpm BV-2).o Discharge flow rate prior to dilution of 35 gpm for the Liquid Waste Effluent Monitor (RM- I LW- 104).

Beaver Valley Power Station ProcdureCNumber:

1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 10 of 40* Discharge flow rate prior to dilution of 15 gpm for the Laundry and Contaminated Shower Drains Monitor [RM-1LW-1 16].The above setpoints for [RM-1LW-104]

and [RM-1LW- 116] can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows: 42F HHSP-f[1.1(1)-1]

where: HHSP = Monitor HIGH-HIGH Alarm Setpoint above background (ncpm).542 542 542= Most restrictive proportionality constant based on nominal flow conditions:

= 3.53E+5 ncpm x 35 gpm +22,800 gpm [RM-1LW-104]

= 8.24E+5 ncpm x 15 gpm +22,800 gpm [RM-1LW-116]

F = Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release through the Emergency Outfall Structure).

f = Discharge flow rate prior to dilution (gpm).8.1.1.1.1 BV-1 Mix Radionuclides The "mix" (radionuclides and composition) of the liquid effluent was determined as follows:* The liquid source terms that are representative of the "mix" of the liquid effluent were determined.

Liquid source terms are the radioactivity levels of the radionuclides in the effluent from ATTACMENT A Table 1.1-I a." The fraction of the total radioactivity in the liquid effluent comprised by radionuclide

'T' (Si) for each individual radionuclide in the liquid effluent was determined as follows: Si _ Ai[E2 Ai i where: Ai = Annual release of radionuclide

'T' (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1.1-l a.

Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 11 of 40 8.1.1.1.2 BV-1 Maximum Acceptable Concentration (All Radionuclides)

The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (C,) was determined by: Ct- F [.()3 fY Si i OECi where: F = Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release through the Emergency Outfall Structure).

= 22,800 gpm = (15,000 gpm ByV- I + 7,800 gpm BV-2)f = Maximum acceptable discharge flow rate prior to dilution (gpm).= 35 gpm for Liquid Waste Effluent Monitor [RM-1LW-104].

= 15 gpm for Laundry and Contaminated Shower Drains Monitor [RM-ILW- 116].OEC, = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-1a. The OEC is set at 10 times the 10 CFR 20, Appendix B (20.1001-20.2402)

Table 2, Col. 2 EC values.Si = The fraction of total radioactivity attributed to radionuclide "i", from Equation [I.1 (1)-2].8.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide"i" in the liquid effluent prior to dilution (Ci) was determined by: Ci = Si Ct [1.1(1)-4]

Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: I1 12 12 of 40 8.1.1.1.4 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the radionuclides; (CR) was determined by: CR = ECi E [1.1(1)-5]

i where: E, = Detection efficiency of the monitor for radionuclide "i" (cpm/uCi/ml) from ATTACHMENT A Table 1.1-1 a. If not listed there, from Calculation Package ERS-SFL-92-039.

(3.1.1.4)8.1.1.1.5 BV- I Monitor HHSP The monitor HHSP above background (ncpm) should be set at the CR value.Since only one tank can be released at a time, adjustment of this value is not necessary to compensate for release from more than one source.8.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HHSP Alarm Setpoint based on this flow rate for the Liquid Waste Effluent Monitor[RM- I LW-I104] and the Laundry and Contaminated Shower Drains Monitor[RM- 1LW- 1161 during all operational conditions.

The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow rate is reduced by the same factor.When the discharge flow rate is limited by the radwaste discharge pump rate capacity or by administrative selection rather than the allowable flow rate determined form activity concentration, the alarm setpoint will be proportionally adjusted based upon the excess dilution factor provided.

Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skil Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 13 ,of 40 8.1.1.2.1 BV-1 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by: f- F [1.1(1)-6]

1.25 E CS i OECi where: F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown (gpm).The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges are administratively prohibited.

Ci = Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uCi/ml) from analysis of the liquid effluent to be released.1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.OECi = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-1 a. The OEC is set at 10 times the 10 CFR 20, Appendix B (20.1001-20.2402)

Table 2, Col.2 EC values.8.1.1.2.2 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the radionuclides, (CR) is determined by: CR = 1.25 E' Ci Ei [1.1(l)-7]

where: Ei = The detection efficiency of the monitor for radionuclide "I" (cpm/uCi/ml) from ATTACHMENT A Table 1.1- Ia. If not listed there, from Calculation Package ERS-SFL-92-039." 3 14)1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.

Beaver Valley Power Station ProcedureN,,boC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 1 14 of 40 8.1.1.2.3 BV-I Monitor HHSP The liquid effluent monitor HHSP above background (ncpm) should be set at the CR value adjusted by any excess dilution factor provided as defined in the following equation: HHSP = CR f [1.1(1)-8]

f, where: HHSP = Monitor HHSP above background.

CR = Calculated monitor count rate (ncpm) from equation [ 1.1 (1)-7].f = Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(1)-6].

f = Actual maximum discharge flow rate to be maintained for the discharge.

The reduced value of f` may be due to pump limitations or administrative selection.

8.1.2 BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH Alarm Setpoint (HSP) that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the ECs specified in 10 CFR 20, Appendix B (20.1001-20.2402), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases. (3.12.6)The methodology described in Section 8.1.2.2 is an alternative method to be used to determine the [2SGC-RQ100]

monitor HSP. The methodology in Section 8.1.2.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid effluent prior to dilution exceeds 1. 14E-3 uCi/ml. This concentration is equivalent to a monitor response and HSP derived in Section 8.1.2.1 and allows for a tritium concentration of up to 2.16E+0 uCi/ml. The setpoint was obtained by use of a conversion factor of 5.61E-9 uCi/ml/cpm determined for the nuclide mix.(3 1.2 6)

Beaver Valley Power Station Procedure Nubr:ODC201 Title: Unit: Lve Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 15 of 40 8.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix The Alarm Setpoints shall be set at the values listed in the following Table: BV-2 LIQUID MONITOR SETPOINTS uCi/ml Above Background Monitor DV HSP ASP Liquid Waste Effluent 2SGC-RQ100 1.14E-3 < 1.4E-3 < 7.99E-4 Monitor Service Water Monitor 2SWS-RQ101 4.30E-5 < 4.30E-5 < 3.01E-5 Service Water Monitor 2SWS-RQ102 4.30E-5 < 4.30E-5 < 3.01E-5 The setpoint for [2SGC-RQ100]

is based on the following conditions, however, the setpoint bases for [2SWS-RQ101]

and [2SWS-RQ 102] can be found in Calculation Package ERS-ATL-93-021 (33126)" Source terms given in ATTACHMENT A Table 1.1-lb. These source terms (without Zn-65) have been generated by using models and input similar to NUREG-0017.

The inputs are given in 1/2-ODC-3.01.

The Zn-65 source term was generated via Calculation Package No. ERS-ATL-93-021.

(3.1.2.6, 3.1.3.13)* Dilution water flow rate of 22,800 gpm = (15,000 gpm BV-I + 7,800 gpm BV-2)." Discharge flow rate prior to dilution of 80 gpm for the Liquid Waste Effluent Monitor [2SGC-RQI00]." A software conversion factor of 5.61E-9 uCi/mllcpm associated with Liquid Waste Effluent Monitor [2SGC-RQ 100].1(31.16)

The above setpoint for [2SGC-RQ100]

can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows: HSP = 4.OOE-6 F f[1.1(2)-1]

where: HSP= HSP (uCi/ml) above background.

4.OOE-6 = Proportionality constant based on nominal flow conditions:

4.OOE-6 = 1.14E-3 net uCi/ml x 80 gpm -22,800 gpm F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown Rate (gpm).f= Discharge flow rate prior to dilution (gpm).

Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 16 of 40 8.1.2.1.1 BV-2 Mix Radionuclides The "mix" (radionuclides and composition) of the liquid effluent was determined as follows: The liquid source terms that are representative of the "mix" of the liquid effluent were determined.

Liquid source terms are the radioactivity levels of the radionuclides in the effluent from ATTACHMENT A Table 1.1-lb.* The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "1" (Si) for each individual radionuclide in the liquid effluent was determined as follows: Si = Ai [1.1(2)-2]

E Ai where: Ai =Annual release of radionuclide

'T" (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1.1-lb.8.1.2.1.2 BV-2 Maximum Acceptable Concentration (All Radionuclides)

The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (Ct) was determined by: Ct- F [1.1(2)-3]

f i Si OECi where: F = Dilution water flow rate (gpm), BV-I plus BV-2 Cooling Tower Blowdown Rate (not including release out through the Emergency Outfall Structure).

= 22,800 gpm = (15,000 gpm BV-1 + 7,800 gpm BV-2).f = Maximum acceptable discharge flow rate prior to dilution (gpm).= 80 gpm for Liquid Waste Process Effluent Monitor [2SGC-RQ100].

OECi = The ODCM liquid effluent concentration limit for radionuclide

'T'(uCi/mi) from ATTACHMENT A Table 1.1-Ib. The OEC is set at 10 times the 10 CFR 20, Appendix B (20.1001-20.2402)

Table 2, Col. 2 EC values.Si = The fraction of total radioactivity attributed to radionuclide "i", from Equation [1.1 (2)-2].

Beaver Valley Power Station Procedure NubrODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1_12 17 of 40 8.1.2.1.3 BV-2 Maximum Acceptable Concentration (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide"i" in the liquid effluent prior to dilution (Ci) was determined by: Ci = Si Ct [ 1.1 (2)-4]8.1.2.1.4 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides; (DV), was determined by: DV = 5.61E-9 Ei Ci Ei [1.1(2)-51 where: 5.61E-9 = Conversion factor (uCi/ml/cpm), an average determined for the source term mix.E,4 = Detection efficiency of the monitor for radionuclide "i" (cpmrruCi/ml) from ATTACHMENT A Table 1.1-lb. If not listed there, from Calculation Package ERS-SFL-86-026.(3 1 .2.2)8.1.2.1.5 BV-2 Monitor HSP The monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the DV value.8.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH Alarm Setpoint based on this flow rate for the Liquid Waste Effluent Monitor (2SGC-RQ100) during all operational conditions.

The monitor alarm setpoint is set slightly above (a factor of 1.25) the concentration reading that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow rate is reduced by the same factor.When the discharge flow rate is. limited by the radwaste discharge pump rate capacity or by administrative selection rather than the allowable flow rate determined form activity concentration, the alarm setpoint will be proportionally adjusted based upon the excess dilution factor provided.

Procedure Number: Beaver Valley Power Station 1/2-ODC-2.o1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 18 of 40 8.1.2.2.1 BV-2 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by: f- F [1.1(2)-6]

1.25 Ei Ci OECi where: F = Dilution water flow rate, BV-I plus BV-2 Cooling Tower Blowdown (gpm).The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges from both plants are administratively prohibited.

Ci = Radioactivity concentration of radionuclide

'"I in the liquid effluent prior to dilution (uCi/ml) from analysis of the liquid effluent to be released.1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.OECi = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from Table 1.1-lb. The OEC is set at 10 times the 10 CFR 20, Appendix B (20.1001-20.2402)

ATTACHMENT A Table 2, Col. 2 EC values.

Beaver Valley Power Station Procedure Number: I/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 19 of 40 8.1.2.2.2 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides; (DV) is determined by: DV = (1.25) (5.61E-9)

Ei Ci Ei where:[1.1(2)-7]

B, = The detection efficiency of the monitor for radionuclide "i" (cpm/uCi/ml) from ATTACHMENT A Table 1.1- lb. If not listed there, from Calculation Package ERS-SFL-86-026.(3.1.2.2) 1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.5.61E-9 = Conversion factor (uCiiml/cpm), an average determined for the source term mix.8.1.2.2.3 BV-2 Monitor HSP The liquid effluent monitor HSP above background (uCi/ml) should be set at the DV value adjusted by any excess dilution factor provided as defined in the following equation: HSP = DV f f`[1.1(2)-81 where: HSP = HSP above background.

DV = Calculated monitor concentration reading (uCi/ml) from equation[1.1(2)-7].

F = Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(2)-6].

f` = Actual maximum discharge flow rate to be maintained for the discharge.

The reduced value of f` may be due to pump limitations or administrative selection.

Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 20 of 40 8.2 Compliance With 10 CFR 20 EC Limits (ODCM CONTROL 3.11.1.1)8.2.1 Batch Releases 8.2.1.1 Pre-Release The radioactivity content of each batch release will be determined prior to release in accordance with 1/2-ODC-3.03, Table 4.11-1. In order to assure representative samples, at least two tank volumes of entrained fluid from each tank to be discharged shall be recirculated.

To meet this requirement tank recirculation time is calculated using actual tank volumes and recirculation pump capacity.

BV-1 and BV-2 will show compliance with ODCM Control 3.11.1.1 in the following manner: The activity of the various radionuclides in the batch release, determined in accordance with 1/2-ODC-3.03, Table 4.11-1, is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: Conci = C 1 R [1.2-1]MDF where: Conci = Concentration of radionuclide "i" at the unrestricted area (uCi/ml).Ci = Concentration of radionuclide "i" in the potential batch release (uCi/ml).R = Release rate of the batch (gpm).MDF = Minimum dilution flow (gpm). (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administratively prohibited).

The projected concentrations in the unrestricted area are compared to the OECs.Before a release is authorized, Equation [1.2-2] must be satisfied.

Yi (Conci/OECi)

< 1 [1.2-2]where: OECi = The ODCM effluent concentration limit of radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-la and 1.1-lb. The OEC is set at 10 times the 10 CFR 20, Appendix B, (20.1001-20.2402)

Table 2, Col. 2 EC values.(3.1.1.3,3.1.2.1)

Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 1 21 of 40 8.2.1.2 Post-Release Following release from the batch tank, the Post Dose calculated in the following manner: PDCF = (VA,)/(DFA)(Vlt)/(DFI)

Correction Factor will be[1.2-3]where: PCDF = Post Dose Correction Factor.VA, = Actual Volume of tank released (gal).DFA = Actual Dilution Flow during release (gpm).VIt = Initial Volume authorized for release (gal).DFI = Initial Dilution Flow authorized for release (gpm).The concentration of each radionuclide following release from the batch tank will be calculated in the unrestricted area in the following manner when the Post Dose Correction Factor shown in equation [1.2-3] is >1: The average activity of radionuclide "i" during the time period of release is divided by the actual dilution flow during the period of release to obtain the concentration in the unrestricted area. This calculation is shown in the following equation: Concik -Cik Vtk ADFk[1.2-4]where: Concik = The concentration of radionuclide "i" (uCi/ml) at the unrestricted area, during the release period of time k.NOTE: Since discharge is from an isolated well-mixed tank at essentially a uniform rate, the difference between average and peak concentration within any discharge period is minimal.Cik = Concentration of radionuclide "i" (uCi/ml) in batch release during time period k.Vtk = Volume of Tank released during time period k (gal).ADFk = Actual volume of Dilution Flow during the time period of release k (gal).

Beaver Valley Power Station ProcedureoNumber-1/2-ODC-2.01 Title: Unit: Level Of se: 1/2 General SEiLE Reference ODCM: LIQUID EFFLUENTS Revision:

Page.Number:

12 22 of 40 To show compliance with ODCM CONTROL 3.11.1.1, the following relationship must be satisfied:

Ei(Concik/OECi) 1 [1.2-5]8.2.2 Continuous Releases Continuous releases of liquid effluents do not normally occur at BV-I or BV-2. When they do occur, the concentration of various radionuclides in the unrestricted area would be calculated using Equation [1.2-1i with Cik, the concentration of isotope i in the continuous release. To show compliance with ODCM CONTROL 3.11.1.1, Equation [1.2-5] must again be satisfied.

8.3 Compliance

With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.1.2 And 3.11.1.3)BV-1 and 2 utilize the concept of a shared liquid radioactive waste system according to NUREG-0133.1 3.3 1 3 This permits mixing of the liquid radwaste for processing.

Since the resulting effluent release cannot accurately be ascribed to a specific reactor unit, the treated effluent releases are allocated as defined below.8.3.1 Cumulation Of Doses (ODCM CONTROL 3.11.1.2)The dose contribution from the release of liquid effluents will be calculated monthly for each batch release during the month and a cumulative summation of the total body and organ doses will be maintained for each calendar month, current calendar quarter, and the calendar year to date. The dose contribution will be calculated using the following equation: D, = UAF E Air' EmAtk Cik Fk [1.3-1]i k=1 where: D, = The cumulative dose commitment to the total body or any organ, t, from the liquid effluents for the total time period m E Atk (mrem)k=1 Atk = The length of the kth release over which Ck and Fk are averaged for all liquid releases (hours).Cik = The average concentration of radionuclide, "I" (uCi/ml), in undiluted liquid effluent during time period Atk from any liquid release.Ai, = The site related ingestion dose commitment factor to the total body or any organ ,r for each identified principal gamma and beta emitter (mrem-ml per hr-uCi)from ATTACHMENT B Table 1.3-1.

Procedure Number: yPower Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 23 of 40 m = Number of releases contributing to the cumulative dose, Dt.UAF = Unit allocation factor. Provides apportionment of dose between BV-1 and BV-2. Normally set at 0.5 for each unit. (Must total to < 1.0).Fk = The near field average dilution factor for Cik during any liquid effluent release.Defined as the ratio of the average undiluted liquid waste flow to the product of the average flow from the site discharge structure during the report period to unrestricted receiving waters, times 3. (3 is the site specific applicable factor for the mixing effect of the BV-1 and BV-2 discharge structure).

-Waste Flow (3)(Dilution Water Flow)The site specific applicable factor of 3 results in a conservative estimate of the near field dilution factor based upon Regulatory Guide 1.113 (3.'34) methodology and is a factor of 10 below the limit specified in NUREG-0133, Section 4.3.31)The dose factor Ai, was calculated for an adult for each isotope using the following equation from NUREG-0133.(3'3.-Ai-r= 1.14E5 (730/D, + 21BFi)DFi, [1.3-21 where: 1 ___.14E5 = ElE6pCi x [ 1E3ml lyr uCi liter _8760 hr j 730 = Adult water consumption rate (liters/yr).

DW = Far field dilution factor from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption.

21 = Adult fish consumption (kg/yr).BFi = Bioaccumulation factor for radionuclide "i" in fish from Table A-1 of Regulatory Guide 1.109('1- (pCi/kg per pCi/1). However, if data was not available from that reference, it was obtained from Table 6 of UCRL-50564.C3

.3.8)The bioaccumulation factor for niobium (300 pCi/kg per pCi/1) was not obtained from either of the above references noted. It was obtained from IAEA Safety Series No. 57. Justification for use of this value is documented in Appendix A to Calculation Package No. ERS-ATL-83-027.'

3 6 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 24 of 40 DFi, = Dose conversion factor for radionuclide "i" for adults for a particular organ 't (mrem/pCi) from Table E- 11 of Regulatory Guide 1.109, .3.5) or NUREG-0172.('3.)1.37 A table of A, values for an adult at BV-1 and BV-2 are presented in ATTACHMENT B Table 1.3-1.The far field dilution factor (Dw) for BV-I and BV-2 is 200. This value is based on a total dilution factor of 600 applicable to the Midland water intake located 1.3 miles downstream and on the opposite bank from BV-1 and BV-2 (i.e., 200 = 600 + 3). The total dilution factor of 600 represents a conservative fully mixed annual average condition.

Since the Midland intake is located on the opposite bank and is below the water surface, essentially fully mixed conditions would have to exist for the radioactive effluent to be transported to the intake.The cumulative doses (from each reactor unit) for a calendar quarter and a calendar year are compared to ODCM CONTROL 3.11.1.2 as follows: For the calendar quarter, D, < 1.5 mrem total body [1.3-3]D, <5 mrem any organ [1.3-4]For the calendar year, D, < 3 mrem total body [1.3-5]D, < 10 mrem any organ [1.3-6]If any of the limits in Equation [1.3-3] through [1.3-6] are exceeded, a Special Report pursuant to ODCM Control 3.11.1.2 of 1/2-ODC-3.03 is required.(3 1 3'2 8.3.2 Projection Of Doses (ODCM CONTROL 3.11.1.3)Doses due to liquid releases shall be projected at least once per 31 days in accordance with ODCM CONTROL 3.11.1.3 and this section. The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge, when the projected doses due to liquid effluent releases from each reactor unit, when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses used in the projection are obtained according to equation [1.3-1]. The 31-day dose projection shall be performed according to the following equations:

When including pre-release data, D 3 1=[A+B] 31+/-C [1.3-7]Tr Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 25 of 40 When not including pre-release data, D 3 1 31+/-C [1.3-8]where: D 3 1 = Projected 31 day dose (mrem).A = Cumulative dose for quarter (mrem).B = Projected dose from this release (mrem).T = Current days into quarter.C = Value which may be used to anticipate plant trends (mrem).8.4 Liquid Radwaste System The liquid radwaste system has the capability to control, collect, process, store, recycle, and dispose of liquid radioactive waste generated as a result of plant operations, including anticipated operational occurrences.

This system also uses some of the components of the steam generator blowdown system for processing.

Simplified flow diagrams of the liquid radwaste systems for BV-1 and BV-2 are provided as ATTACHMENT C Figures 1.4-1 and 1.4-2 respectively.

A diagram showing the liquid effluent release points is provided as ATTACHMENT C Figure 1.4-3. A diagram of the site boundary for liquid effluents is provided as ATTACHMENT D Figure 5-1.Since the concept of a shared liquid radwaste system is used, then any liquid waste generated can be stored, processed and discharged from either BV- I or BV-2.8.4.1 BV-1 Liquid Radwaste System Components 8.4.1.1 [1BR-I-IA/IB]:

Cesium Removal Ion Exchangers There are two of these ion exchangers, each has a capacity of 35 cubic feet. They are located on the east side of the Auxiliary Building (elevation 735'). They receive process fluid (liquid waste) from the reactor coolant system when letdown flow is diverted from the volume control tank.8.4.1.2 [1BR-TK-4A/4B1]:

Coolant Recovery Tanks There are two of these tanks, each tank has a nominal capacity of 195,000 gallons (maximum capacity = 205,578 gallons).

They are located in the Solid Waste Building.

They receive diverted letdown flow from the volume control tank and various reactor plant non-aerated drains that were processed through the cesium removal ion exchangers from both Unit 1 and Unit 2. These tanks can also receive unprocessed liquid wastes from either Unit 1 or Unit 2 liquid waste systems.Normally, one tank receives liquid waste while the other tank is placed on recirculation through the demineralizer until the radioactivity concentration is Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General SUll Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: a t12 f 26 of 40 acceptable for discharge.

A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.1.3 [1LW-TK-2A/2B]:

High Level Waste Drain Tanks There are two of these tanks, each tank has a nominal capacity of 5,000 gallons (maximum capacity = 4,899 gallons).

They are located on the northwest wall of the Auxiliary Building (elevation 735'). They receive liquid wastes from the vent and drain system.8.4.1.4 [1LW-TK-3A/3B]:

Low Level Waste Drain Tanks There are two of these tanks, each tank has a nominal capacity of 2,000 gallons (maximum capacity = 1,998 gallons).

They are located in the northwest corner of the Auxiliary Building (elevation 735'). They receive liquid wastes from the vent and drain system and can be transferred directly to the Coolant Recovery Tanks.Although not normally used, these tanks can also be utilized to discharge processed or unprocessed liquid wastes. A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.1.5 [1LW-FL-6]:

Liquid Waste Pre-Conditioning Filter There is a pre-conditioning filter with a 50 cubic feet capacity.

The main purpose of the pre-conditioning filter is to clean liquid waste water of particulate and dissolved radioactive contaminants that is stored in [1LW-TK-2A/2B], [1LW-TK-3A/3B]

and[lBR-TK-4A/4B].

The pre-conditioning filter can be customized with varying grades of activated charcoal (carbon) intended for removal of radionuclides in a colloidal state. The charcoal may consist of Course Mesh High Activated Coco Carbon, Medium Mesh High Activated Coco Carbon, Fine Mesh High Activated Coco Carbon and Cobalt Selective Media. This filter is located in the Decontamination Building (elevation 735').8.4.1.6 [1LW-I-2]:

Liquid Waste Demineralizer There are four (4) demineralizer vessels each with a capacity of 30 cubic feet. The main purpose of the demineralizer is to clean liquid waste water of particulate and dissolved radioactive contaminants that was stored on site and pre-conditioned by[I LW-FL-6].

Each of the demineralizer vessels can be customized with different resins for effective removal of chemical contaminants along with radioactive contaminants.

Generally, vessels 1 and 2 may contain Cation Resin, vessel 3 may be left empty to accept special resin (e.g., Mixed Bed Resin, Macro-porous Resin, Anion Resin, etc.) and vessel 4 may contain an Antimony Removal Resin. However, resin selection and sequence may be subject to change dependant upon site needs.This demineralizer is located in the Decontamination Building (elevation 735').

Beaver Valley Power Station Prour N17ODCo 2.-Title: Unit: vel Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 27 of 40 8.4.1.7 Liquid Waste Evaporator An evaporator was originally designed to process liquid waste at Unit 1 with a capacity of 6 gpm. However, this evaporator was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste.

SINCE the evaporator is no longer in-use, THEN it is not shown on Figure 1.4-1 in ATTACHMENT C.8.4.1.8 [1LW-TK-7A/7B]:

Steam Generator Drain Tanks There are two of these tanks, each tank has a nominal capacity of 34,500 gallons (maximum capacity = 35,800 gallons).

They are located in the Fuel Pool Leakage Monitoring Room (elevation 735'). They normally receive liquid waste that has been processed through the liquid waste demineralizer.

These tanks can also receive liquid waste from Unit 2. Upon completion of filling operation, the tank is placed on recirculation through the demineralizer until the radioactivity concentration is acceptable for discharge.

A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.1.9 [RM-lLW-104]:

Liquid Waste Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged.

The normal rate of discharge through this radiation monitor from [1LW-TK-3A/3B]

and [1LW-TK-7A/7B]

is <35 gpm. The normal rate of discharge through this radiation monitor from [1BR-TK-4A/4B]

is <50 gpm. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valve.8.4.2 BV-1 Laundry and Contaminated Shower Drain System Components 8.4.2.1 [1LW-TK-6A/6B]:

Laundry and Contaminated Shower Drain Tanks There are two of these tanks, each has a nominal capacity of 1,200 gallons (maximum capacity = 1,303 gallons).

They are located in the northwest corner of the Auxiliary Building (elevation 722'). They receive laundry and contaminated shower drains waste from the Service Building.

These tanks can also receive mop water waste from Unit 2. The waste in these tanks is not sent to the liquid waste demineralizer for cleanup because this waste may contain organic compounds that will deplete a resin bed. Upon completion of filling operation, the tank must be recirculated a minimum of two tank volumes prior to sampling for discharge permit preparation.

Beaver Valley Power Station Procedure Nomber: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: ODM LQIDEFLETS1 12 28 of 40 8.4.2.2 [RM-1LW-1 16]: Laundry and Contaminated Shower Drains Tank Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes laundry and contaminated shower drains waste as it is being discharged.

The normal rate of discharge through this radiation monitor from [1LW-TK-6A/6B]

is <15 gpm. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valve.8.4.3 BV-2 Liquid Radwaste System Components 8.4.3.1 [2BRS-IOE21A/21B]:

Cesium Removal Ion Exchangers.

There are two of these ion exchangers, each has a capacity of 35 cubic feet. They are located on the east side of the Auxiliary Building (elevation 718'). They receive and process liquid wastes from the reactor coolant system during dilution or letdown operations.

8.4.3.2 [2LWS-TK21AI21B]:

Waste Drain Tanks There are two of these tanks, each tank has a nominal capacity of 10,000 gallons (maximum capacity = 10,184 gallons).

They are located in the northeast corner of the Auxiliary Building (elevation 710'). They receive liquid wastes from the vent and drain system. These tanks can also receive liquid wastes from Unit 1. IF further processing is not necessary, THEN it may be placed on recirculation.

A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.3.3 [2SGC-IOE21A/21B]:

Steam Generator Blowdown Cleanup Ion Exchangers The main purpose of the ion exchangers is to clean liquid waste water of particulate and dissolved radioactive contaminants through an ion exchange process. There is a resin bed, outlets strainer, and cleanup filter associated with each of these ion exchangers.

They are located in the Waste Handling Building (elevation 722').8.4.3.4 Liquid Waste Evaporator Two evaporators were originally designed to process liquid waste at Unit 2 with a capacity of 20 gpm each. However, these evaporators were retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste.

SINCE the evaporators are no longer in-use, THEN they are not shown on Figure 1.4-2 in ATTACHMENT C.

Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 29 of 40 8.4.3.5 [2SGC-TK23A/23B]:

Steam Generator Blowdown Test Tanks There are two of these tanks, each has a nominal capacity of 18,000 gallons (maximum capacity = 17,955 gallons).

They are located in the Auxiliary Building (elevation 755'). They receive liquid waste that has been processed through the cleanup ion exchangers.

Upon completion of filling operation, the tank is placed on recirculation through the demineralizer until the radioactivity concentration is acceptable for discharge.

A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.3.6 [2SGC-TK21A/21BI:

Steam Generator Blowdown Hold Tanks There are two of these tanks, each has a nominal capacity of 50,000 gallons (maximum capacity = 51,460 gallons).

They are located in the Waste Handling Building (elevation 722'). These tanks are used to store liquid waste when the radioactive concentration of the steam generator blowdown test tank is not acceptable for discharge.

.These tanks can also receive liquid wastes from Unit 1.The contents of this tank may be drained or processed through the Unit 1 or Unit 2 Liquid Radwaste Treatment System until the radioactivity concentration is acceptable for discharge.

A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.

8.4.3.7 [2SGC-RQ100]:

Liquid Waste Effluent Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged.

The normal rate of discharge through this radiation monitor is <85 gpm. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water leaving the site.If an upper activity alarm is received, it automatically terminates the discharge by closing the discharge line isolation valves.-END -

Procedure Number: yPower Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 30 of 40 ATTACHMENT A Page 1 of 4 LIQUID SOURCE TERMS TABLE 1.1-la BV-I LIQUID SOURCE TERM (4)0z NUCLIDE Cr-51 Mn-54 FR-55 Fe-59 Co-58 Co-60 7r,-65(3.1.3.13)

Np-239 Br-83 Br-84 Br-85 Rbl6 Sr-89 Sr-90 Y-90 Y-91m Y-91 Y-93 Zr-95 Nb-95 Sr-91 Mo-99 Tc-99m Ru-103 Ru-106 Rh-103m Rh-106 Te- 125m Te-127m Te-127 Te-129m Te-129 1-130 Te-131rm Te- 131 1-131 Te-132 1-132 1-133 1-134 Cs-134 ANNUALRELEASE 13E-3 3.1E-4 1.6E-3 83E,4 1.E-2 20E-3 Z69E-2 1.4E-4 25E-5 25E-5 2.7E-6 7-5E-5 2.9E,4 1. 1E-5 9.4E-6 8.7E-6 5.7E-5 7.4E-7 5.1E-5 5.2E-5 1.3E-5 1.1E-2 1.1E-2 3.4E-5 1.OE-5 3.4E-5 1.OE-5 2.5E-5 2.6E-4 2.7E-4 I.IE-3 6.7E-4 1.2E-4 1.6E-4 3E-5 1.6E-1 4.3E-3 4.9E-3 4.OE-2 8.0E-5 4.6E-2 (3)OFC 5E-3 3E-4 1E-3 15A 2E4 3E-5 5E-5 2E4 9E-3 4E-3 (5)7E-5 8E-5 5E-6 7E-5 2E-2 8E-5 2E-4 2E-4 3E-4 2E-4 2E-4 1E-2 3E-4 3E-5 6E-2 (5)2E-4 9E-5 IE-3 7E-5 4E-3 2E-4 8E-5 8E-4 1E-5 9E-5 IE-3 7E-5 4E-3 9E-6 Ei DETECTION EFHCIENCY (cpmkuChml) 1.18E+7 859E+7 (5)9.17E+7 1.16E+8 1.73E+8 4.67E+7 8.49E+7 136E+6 9.75E+7 6.19EB6 (5)(5)(5)(5)8.98E+7 2,60E+5 (5)8.60E+7 8.64E+7 6.97E+7 2.84E+7 8.96E+7 9.5E+7 (5)(5)(5)1.83E+5 4.09E+4 1,.38E+6 4,02E+6 1.1 2E+7 3.08E+8 1.82E+8 1.20E+8 1.11E+8 1.17E+8 2.66E+8 9.90E+7 2.70E+8 1.99E+8 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: evel Of se: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 31 of 40 ATTACHMENT A Page 2 of 4 LIQUID SOURCE TERMS 1-135 Cs-136 Cs-137 Ba-137m Ba-140 La- 140 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 H-3 4.3E-3 8.9E-3 3.3E-2 3. 1E-2 1.1 E-4 1. 1E-4 5.1E-5 2.8E-6 3.2E-5 2.7E-5 3.2E-5 5.50E+2 3E-4 6E-5 IE-5 1E-5 8E-5 9E-5 3E-4 2E-4 3E-5 2E-4 6E-3 1E-2 1.19E+8 2.80E+8 8.01E+7 8.01E+7 4.37E+7 2.OOE+8 5.07E+7 7.27E+7 1.06E+7 1.04E+0 2.25E+6 (5)(1)(2)(3)(4)*(5)TOTAL"' 4.05E-1 Excluding Tritium and Entrained Noble Gases Source Term for (RM-ILW-104 and RM-ILW-1 16) from Stone and Webster Calculation Package UR(B)-160 (3.1.1.6)ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 (3.1.1.3)Detection Efficiency for (RM-ILW-104 and RM-ILW-1 16) from Calculation Package ERS-SFL-92-039 (3 1.1.4)Insignificant Beaver Valley Power Station ProcedureNub Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 32 of 40 ATTACHMENT A Page 3 of 4 LIQUID SOURCE TERMS TABLE 1.1-1b BV-2 LIQUID SOURCE TERN 4I (2)NUCLIDE Cr-51 Mn-54 B--55 Fe-59 Co-58 Co60 7n-_65(3.1.3.13)

Np-239 Br-83 Br-84 Rb-86 Sr-89 Sr-90 Sr-91 Mo-99 Tc-99m Te-125m Te-127m Te-127 Te-129n Te-129 1-130 Te-131m Te-131 1-131 Te-132 1-132 1-133 1-134 Cs-134 1-135 Cs-136 Cs-137 Ba-137m Ba-140 La-140 ANNUAL RELEASE (Qi)1.mDE-4 250E-5 i.30E-4 6-50E-5 1.1OE-3 1.60E-4 5. 10E-2 320E-5 2.90E-5 5.90E-9 3.70E-5 2.20E-5 8-50E-7 5.30E-6 2.30E-3 2.10E-3 1.90E-6 21OE-5 2.50E-5 8.20E-5 530E-5 230E-4 5.20E-5 9.40E-6 1.OOE-1 7.8054 230E-3 6-50E-2 4.60E-6 3.ODE-2 920E-3 3.90E-3 2.20E-2 2,10E-2 930E-6 8.40E-6 (3)OEC_(uCi/mi)5E-3 3E-4 1E-3 1E-4 2E4 3E-5 5E-5 2E-4 9E-3 4E-3 7E-5 8E-5 5E-6 2E-4 2E4 1E-2 2E-4 9E-5 1E-3 7E-5 4E-3 2E-4 8E-5 8E-4 1E-5 9E-5 IE-3 7E-5 4E-3 9E-6 3E-4 6E-5 1E-5 lE-5 8E-5 9E-5 (4)DETECTON 2.01E+7 L27E+S (5)1.26E+8 1.82E+8 2.38E+8 6.50E+7 1.65E+8 2-42E+6 1.38E+8 1.04E+7 1.83E-+4 (5)1 .04E+8 4.47E+7 1.40E+8 3.94E+5 126E+5 2.43E+i6 6-53E+i6 1.96E+47 5.18E+8 285E+i8 1.88E+8 1 .96E+8 i.76E+8 4.22E+8 1.73E+8 4.06E+8 3.25E+8 1.71E+i8 428E+8 1 28E+8 1.33E+8 7.50E+7 3.08E+8 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 12 33 of 40 ATTACHMENT A Page 4 of 4 LIQUID SOURCE TERMS TABLE 1.1- lb (continued)

BV-2 LIQUID SOURCE TERM NUCLIDE Y-90 Y-91m Y-91 Y-93 Zr-95 Nb-95 Ru- 103 Ru-106 Rh-103m Rh-106 Ce-141 Ce-143 Ce-144 Pr- 143 Pr- 144 H-3 TOTAL("'(2)Ai ANNUAL RELEASE (Ci)6.OOE-7 3.60E-6 4.40E-6 3.OOE-7 4.OOE-6 4.OOE-6 2.70E-6 8.20E-7 2.70E-6 8.20E-7 4.OOE-6 8.60E-7 2.60E-6 2.30E-6 2.60E-6 5.50E+2 2.40E- 1 (3)OECi (uCi/ml)7E-5 2E-2 8E-5 2E-4 2E-4 3E74 3E-4 3E-5 6E-2 3E-4 2E-4 3E-5 2E-4 6E-3 1E-2 (4)Ei DETECTION EFFICIENCY (cpm/uCi/ml) 1.59E+8 3.55E+5 2.03E+7 1.35E+8 1.33E+8 1.71E+8 (5)(5)5.65E+7 7.75E+7 1.20E+8 1.87E+7 1.63E+0 3.40E+6 (5).(1)(2)(3)(4)(5)Excluding Tritium and Entrained Noble Gases Source Term for (2SGC-RQ100) from Computer Code LIQ1BB (31.23)ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 (3121)Detection Efficiency for (2SGC-RQ100) from Calculation Package ERS-SFL-86-026 (3122)Insignificant Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 2 34 of 40 ATTACHMENT B Page 1 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Air VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/m!)NUCUDE BONE LVER T-BODY THYROID KIDNEY LUNG GI-61 H-3 O.O0E-01 27E01 2.70E,01 2.7WE,01 270_O1 27CEO1 Z70E-01 C-14 3.13E04 626E03 626E03 626E03 626E03 626E03 626E03 Na-24 4.(,EO2 4.08E02 4.08E02 4.08E02 4.08E02 4.08E02 4.08E02 P-32 4.62E07 2,87E06 1.79E06 OX-F,01 0.00E-01 O.00E-01 5.19E06 Cr-51 O.(E-O01 O.O(E-01 127E(0 7.62E-01 2,81E-01 1.69E00 321E02 Mn-54 O.O(E-01 438E03 835E02 O.O01 130E03 0.XE-01 134E04 Mn-56 O.(XEO1 1.1E02 195E01 0.0E-01 1A.E02 OF.OE01 352E03 Fe-55 6.59E02 456E02 1.06E02 0.00&01 O.WE-O1 254E02 2.61E02 Fe-59 1.04E03 2.45E03 938E02 O.(EOl1 0.000E-1 6.83E02 8.15E03-----------.-.------------------.-..-.---------------.-.----.-.---------------------------------------------------

CO-57 O.0E-01 210E01 3.50E01 0,0(EO1 O.fF_0I1 OE.O(E1 533E02 Co-58 0.00501 8.95E01 2.01E02 O.DOM O.(E-01 O.XE,.01 1.81E03 Co-60 0.IXJE1 257E02 5.67E02 O.IXE-O1 O.0E-O1 O.(XE-O1 4.83E03..............................................................................................................

Ni-63 3.12EO4 2,1EO3 1.05E03 O.tOE,01 0.3013-01 O.fKE-01 4.51E02 Ni-65 127E02 1.65E01 751E00 O.OXE-O1 O.fEO1 O.0_E-01 4.17E02 Cu-64 O.(XF-1 1.00E01 4.70E00 O.XE,O1 252E01 0.Q(E-01 853E02 Zn-65 232EO4 737E04 333E04 O.(XE-01 493E04 O.OtE-O1 4.64E04 Zn-69 4.93E01 9.43E01 656E00 O.XXE-1 6.13E01 O.(fE-O1 1.42E01 Br-83 O.IXEO-01 O.OF,01 4.04E01 O.(iE-01 O.W0E-01 0.00E-O1 5.82E01 Br-84 O.0EO1 O.(IE-01 52AE01 O.(E-O01 0.00E-01 O.cOF,-O1 4.11E-04 Br-85 0.00IE01 O.O0E-01 Z15EO 0.0iiEO1 O.OOE-01 0.0ii0E)1 O.fF_1 Rb-86 0.00E-01 1.01E05 4.71E04 0.(EO1 O.OOE-O1 O.0E-01 1.99E04..............................................................................................................

Rb-88 0.06E-01 2-90E02 154EI2 O.(OE-O1 O.OOE-01 0.00E-01 4.(FE-9Y9 Rb-89 O.(AF,1 1.92E02 135E02 O.OFA1 O.0E-O1 O.OOE,01 1.12E-11 Sr-89 222E04 O.OOE-01 639E02 O.OIE-01 O.OOE-01 O.L(E-O1 3.57E03 Sr-90 5.48E05 O.flE-O1 13,EO5 O.0E-01 O.OtF)1 158E04 Sr-91 4.10E02 O.XDE-OM 1.65E01 O.I0E-01 0.Q0E-01 0.00601 1.95E03 Sr-92 155E02 O.IXE-01 6.72E00 O.iE-A1 O.0E-01 0.XXE-1 3.08E03 Y-90 5,80E.01 O0.E-01 155E,02 O.IXEO1 O.O0E-01 0.00F__1 6.15E03 Y-91m 5.48E,03 O.XE-O01 212E-04 O.OJE-1 O.E-01 Of.iF_01 1.61E402 Y-91 850E00 O.(X-O)1 227F_01 0.00E-01 0.00E-01 0X0E-01 4.68E03 Y-92 5.09E,02 O.0E-01 1.49E-03 O.fXE-01 O.00E-01 0.00E-01 8.92E02 Y-93 1.62E-01 0.0XE-OI 4A6E-03 O.(_E-O1 O.WE-01 O.0FAO1 5.12E03 Zr-95 253F_01 8.1 IME2 5.49E-02 O.OOE-01 127E-01 O.0E-01 257E02 Zr-97 1.40E-02 2.82E-03 129E-03 O.0XEO01 426E-03 0.XFAI1 8.73E02 Nb-95 4.47E00 2.49E00 1-34E00 O.E-01 2.46E00 O.XE-01 1_51E04 Nb-97 3.75E02 9.49E-03 3.46E-03 O.(XE-01 1.11E-02 O.XCE-01 350E01 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1_12 35 of 40 ATTACHMENT B Page 2 of 3 INGESTION DOSE COMMITMENT FACTORS Ai, VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/ml)NUCUDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-_LI Mo-99 O.i0E-01 1.05E02 Z00E01 O.fKE.01 238E02 O.I0E-01 243E02 Tc-99m 8.97E,03 254E-02 323E,01 O(KIE_01 3.85E-01 124E02 15(E01 Tc-101 923F-03 133E-02 130601 O.(EO01 239E3-01 6.79E303 4.(XF-14.................................................................................................................

Ru-103 451E00 0.0AE01 194E13) 0.00_E01 1.72E01 0.0013-01 526E02 Ru-105 3.75E-01 O.0fE-01 1.48E-01 0.00E-01 4.85E00 0.00F_301 229E02 Ru-106 6.70E01 0.00E-01 8.48E0) O.E-01 129E02 O.{0E-01 434E 03................................................................................................................

Rh-103m 451E00 0.0)E-01 1.94E00 0.0IE_01 1.72E01 0.(Fc&01 526E302 Rh-105 295E10) Z(1E0 1.42E00 0.JE-1 9.16E00 0.0)E-01 3.43E02 Rh-106 6.70E01 O.LXE-01 8.48E00 0.0(C&01 129E02 0.00E-01 434E00-------------------------------.-.-------------------------------------------------------------------------------

Ag-li0n 9.48E,01 8.77E-01 521E-01 O.O(XF_1 1.72E100 0.fFA)1 358E02 Sb-124 7.87E00 1.49E,01 3.12E30) 1.91E_02 0.O0FE01 6.13E0) 223E02 Sb-125 5.03E30 5.62E-02 120E00 5.11E5-03 0.00F_,01 3.88E00 554E01 Sb-126 323E00 658F_-02 1.17E00 1.981.02 0.00E,01 1.98E00 264E02 Sb-127 725E_01 159E,02 2.78F-01 8.71E,03 0.00E-01 43(.,01 1.66E-02 Te-125m 2-57E103 93(E02 3.44E02 7.72E132 1.04E04 O{K-0. 1 1.03E04 Te-127m 6.49E03 232E03 7.90E02 1.66E3C 2.63E04 00.1-,01 2.17E04 Te-127 1.05E02 3.78E01 228E01 7.81E01 429E02 0.00E-01 832E03 Te-129m 1.103E04 4.11E03 1.74E03 3.78E03 4.60E04 O.OXE-01 555E04 Te-129 3.01E01 1.13E01 733E00 231E01 126E02 O.0E.O1 227E01 Te-131m 1.66E03 8.1E02 6.75E02 128E03 821E03 O.XE-O1 8.05E04 Te-131 1.89E01 7.88E00 5.96E00 1-55EO0 827E01 .00E,-01 2-67E00 Te-132 241E03 15603 1.47E03 1.72E03 150E04 0.00F_01 739E04 Te-134 3.10E01 203E01 125E101 71E01 196E02 0.I)E-01 3.44E-02 1-129 1.19E02 1.02E02 335E02 263E05 2.19E02 0.(0F_01 1.61E01 1-130 2.75E01 8.10E01 3.20E01 6.87E03 126E02 O).0_.01 6.97E01 1-131 151E02 2102 124E02 7.08E04 3.71E02 0.(XE0,1 5.70E01 1-132 7.37E00 1.97E01 6.90E30 6.90EO2 3.14E01 0.00B01O1 3.71E0)1-133 5.16E01 8.97E01 274E01 132E04 157E02 0.AE-01 8,05E01 1-134 3.85E10 1.05E01 3.74E00 1.81E02 1.66E01 O(X0E-01 9.12E,03 1-135 1.61E01 421E01 155E01 2781E03 6.76E01 0.130E-01 4.76E01 Cs-134 2.98E05 7.09E05 5.79E05 O.XFO1 229E05 7.61E04 124E104 Cs-136 3.12E04 1.23E05 8.85E04 O.IXE-01 6.85E04 939E03 1.40E104 Cs-137 3.82E05 5221305 3.42E05 O.0E-O01 1.77E05 5.89E04 1.01E04 Cs-138 264E02 522E02 259E02 O.0E-01 3.84E02 3.79E01 223E-03 Ba-139 9.69E-01 6.90E-04 2.84E-02 O.C(IF_01 6.45E-04 3.92E-04 1.72E00 Ba-140 203E02 255E-01 133E01 0.0-FA)1 8.66E)02 1.46E-01 4.18E02 Beaver Valley Power Station Procedure Number: 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: 1 12 36 of 40__ _ ___ _ -- ATTACHMENT B Page 3 of 3 INGESTION DOSE COMMITMENT FACTORS Ai VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mremlhr per uCilml)NUCIIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LIL Ba-14] 4.71F,01 336E-04 159E-02 OfX0E-01 331B014 202E-04 222E-10 Ba-142 2,13E-01 219E-04 134E,02 O.AXE-01 1.8513-04 124E-04 3.OOiE-19 La-1z1O 151E,01 759E-02 ZOIE-02 O.00Ffi0 QOJOE-Ol QOJOE-Ol 557E03 La-142 7.71M-0 35113-03 8.74E,04 O.IXE-O1 O.OX1E-O1 O.00m].O 256E01 Ce,-141 2.6313-02 1.78E,02 Z02503 O.OXE-01 826E.03 O.00E-01 6.80EO1 Ce-143 4.64E-03 3.43EWO 3.79EFO4 O.AXE-O1 1.51E-03 OfiJE-Ol 128E02 Ce-144 13ME 00 5.7350O1 736E,02 O.IXE-O1 3.401E-01 OXUOIE0 4.64E02 Pr-143 5-54E.O 2.22E-O1 2.75E,02 O.IXE-O1 128E-01 OIIUE-O1 2.43E03 Pr-144 1.81E,03 7-535-04 922E-05 O.OXF-01 425E-04 Q.IUE-O1 2.61E-10 Nd-147 3.79E-01 43&E-01 2.62E.02 GOCE-01 2-5kE-O1 Q.OFl-1 2.10E03 Pmn-147 454EOID 427E-01 1.73501 Qa0E-1. 8.08E-01 OAXOE-01 538E02 Pinm149 9.16B492 L3KE-02 5295-03 .00E-01 2.4513-02 OXXOFBO1 243E03 Sm-151 4.16EOO 7.1713-01 1.72E-01 O.XJE-01 8.0213-01 QWOE-O1 3.17E02 Srn-153 5.16E-02 431E-02 3.15E.03 O.fKE-O1 139E.02 O.OJE-O1 154E03 W-187 2.96E02 2.47E02 8.65E01 O.OtE-O1 OIIXIE-O1 O.OOE-01 8.10E04 Np-239 2.90E-02 285E-03 1-57E,03 OIXOO01 8.89E-03 MflEOM 5.85E02 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number:-12 1 37 of 40 ATTACHMENT C Page 1 of 3 LIQUID RADWASTE SYSTEM FIGURE 1.4-1 BV-1 LIQUID RADWASTE SYSTEM STREAM UNIT 1: COLLECTION, TREATMENT, & DISCHARGE Reactor Coolant Cesium Coolant Recovery Tanks Letdown or 10 Removal Ion Reactor Plant Exchangers IBR-TK-4A/4B non-aerated BR-I-i A/1 B 195,000 gal/tank drains _Containment Sump [ Waste Drains Tanks _ Liquid Waste Ion ATTACHMENT C Page 2 of 3 LIQUID RADWASTE SYSTEM FIGURE 1.4-2 BV-2 LIQUID RADWASTE SYSTEM STREAM UNIT 2: COLLECTION, TREATMENT, & DISCHARGE Containment Sump Liquid Waste Drains Tanks Liquid Waste Ion Exchanger Resin Vessels, Clean-up Filters and Strainers Steam Generator Blowdown Test Tanks Aux Bldg Sumps 2LWS-TK21A/21B 10,000 gal/tank 2SGC-TK23A/23B 18,000 gal/tank Miscellaneous Sourcesl 2SGC-IOE21A/21B Reactor Plant Samples Laboratory Drains Condensate Demineralizer Rinse Water BVPS 1&2 Combined Cooling Tower Discharge Point 22,800 gpm Procedure Number: Beaver Valley Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number: I 1]2__ 39 of 40 ATTACHMENT C Page 3 of 3 LIQUID RADWASTE SYSTEM FIGURE 1.4-3 BV-1 AND 2 LIQUID EFFLUENT RELEASE POINTS Beaver Valley Power Station Pocedure Nuombor 1/2-ODC-2.01 Title: Unit: Lvel Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:

Page Number:.1 12 1 40 of 40 ATTACHMENT D Page 1 of 1 SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 5-1 SITE BOUNDARY FOR LIQUID EFFLUENTS