L-21-135, ODCM: Liquid Effluents
| ML21127A167 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/17/2020 |
| From: | Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21127A168 | List: |
| References | |
| L-21-135 | |
| Download: ML21127A167 (43) | |
Text
RTL #A9.621B Beaver Valley Power Station Unit 1/2 l/2-0DC-2 .01 ODCM: LIQUID EFFLUENTS Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 18 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 07/17/20
Proccduro Number:
Beaver Valley Power Station l/2-0DC-2.01 Trtlo: Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number.
lR 2nf.1l TABLE OF CONTENTS 1.0 PURPOSE ......................................................................................................................................... 3 2.0 SCOPE .............................................................................................................................................. 3
3.0 REFERENCES
AND COMMITMENTS ......................................................................................... 3 3.1 References .............................................................................................................................. 3 3 .2 Commitments ......................................................................................................................... 6 4.0 RECORDS AND FORMS ................................................................................................................ 7 4.1 Records ................................................................................................................................... 7 4.2 Forms ...................................................................................................................................... 7 5.0 PRECAUTIONS AND LIMITATIONS .......................................................................................... 7 5.1 Precautions ............................................................................................................................. 7 5.2 Limitations .............................................................................................................................. 7 6.0 ACCEPTAN"CE CRITERIA ............................................................................................................. 8 7.0 PREREQUISITES ............................................................................................................................ 8 8.0 PROCEDURE ................................................................................................................................... 8 8.1 Alarm Setpoints ...................................................................................................................... 8 8.1.1 BV-1 Monitor Alarm Setpoint Determination ....................................................... 8 8.1.2 BV-2 Monitor Alarm Setpoint Determination..................................................... 14 8.2 Compliance With 10 CPR 20 EC Limits (ODCM CONTROL 3 .11.1.1) ............................ 20 8.2.1 Batch Releases ..................................................................................................... 20 8.2.2 Continuous Releases ............................................................................................ 22 8.3 Compliance With 10 CPR 50 Dose Limits (ODCM CONTROLS 3.11.12 And 3.11.1.3).22 8.3.1 Cumulation Of Doses (ODCM CONTROL 3.l 1.l.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 .............. 29 8 .4.3 BV-2 Liquid Radwaste System Components ...................................................... 29 8.4.4 BV-1/2 Miscellaneous Sumps ............................................................................. 31 ATTACIIME NT A LIQUID SOURCE TERMS .............................................................................. 33 ATTACHME NT B INGESTION DOSE CO;MMITMENT FACTORS ........................................ 37 ATTACHME NT C LIQUID RADWASTE SYSTEM ..................................................................... 40 ATTACHME NT D SITE BOUNDARY FOR LIQUID EFFLUENTS ........................................... 43
Proccdurc Number:
Beaver Valley Power Station l/2-0DC-2.01
Title:
Unit Lcvc1 Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS R.evis:lon: PageNwmcr:
lR 3 nf.d.~
1.0 PURPOSE 1.1 This procedure provides the methodology to calculate dose, release concentrations, and alarm setpoints from liquid effluents in accordance with the requirements of in Beaver Valley Technical Specifications [TS] 5.5.2. (3.2.1)
I.I.I Liquid effluent monitor alarm setpoints [TS] 5.5.2.a 1.1.2 Liquid effluent release concentration calculations [TS] 5 .5 .2.b) 1.1.3 Liquid effluent dose projection and cumulative dose calculations [TS] 5.5.2.d and
[TS] 5.5.2.e 1.1.4 Liquid Radwaste Treatment System [TS] 5.5.2.f 1.1.5 Site Boundary used for liquid effluents 2.0 SCOPE 2.1 This procedure is applicable to liquid effluents at Beaver Valley Power Station.
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 Calculation Package No. ERS-SFL-92-039, Isotopic Efficiencies For Unit 1 Liquid Process Monitors 3.1.2 References for BV-2 Liquid Effluent Monitor Setpoints 3.1.2.1 Calculation Package No. ERS-SFL-86-026, Unit 2 ORMS Isotopic Efficiencies 3.1.2.2 Stone and Webster Computer Code LIQIBB; "Normal Liquid Releases From A Pressurized Water Reactor" 3.1.2.3 Calculation Package No. ERS-JWW-87-015, Isotopic Efficiencies For 2SGC-RQIO0 3 .1.2.3. I The Isotopic Efficiencies for 2SGC-RQ 100 are superseded by the values presented in Calculation Package No. ERS-SFL-86-026.
Beaver Valley Power Station Proccdurc Number.
1/2-0DC-2 .01 Unit Level OfUsc:
1/2 General Skill Reference ODCM:Ll QUIDEFF LUENTS Revision: PageNumber:
18 4ofA.1 3.1.2.4 Calculation Package No. ERS-WFW-87-021, Conversion Factor for 2SGC-RQ100 3.1.2.4.1 The Monitor Conversion Factor (CFu) for 2SGC-RQ1 00 is superseded by the value presented in Calculation Package No. ERS-ATL-93--021.
3 .1.3 References used in other sections of this procedure 3.1.3.1 NUREG--0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89--01, Supplement No. 1) 3.1.3.3 NUREG-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 Implement ing 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 Complianc e to 10 CPR Part 50, Appendix I 3.1.3.6 Calculation Package No. ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for 1/2-ENV-05.06 3.1.3.7 Calculation Package No. ERS-ATL-93-021, Process Alarm Setpoints For Liquid Effluent Monitors 3 .1.3 .8 Calculation Package No. ERS-LMR-15-006, Additional Effluent Dose Factors 3.1.3.9 Stone and Webster Calculation Package No. UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations - Expect and Design Cases (per Unit and Site) 3.1.3.10 10 CPR 20, Appendix B, (20.1001-20.2402) Table 2, Column 2 EC's 3 .1.3.11 NUREG-0172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake 3 .1.3 .12 UCRL-50564; Concentration Factors of Chemical Elements in Echble Aquatic Organisms, Revision I, 1972 3.1.3.13 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.3.14 l/2-ADM-0 100, Procedure Writers Guide 3.1.3.15 NOP-SS-3001, Procedure Review and Approval
Bea ver Valley Pow er Station Procedure Number:
Title:
l/2-0D C-2.0 1 Unit Level Of Use:
1/2 General Skill Reference ODCM : LIQUID EFFLU ENTS Revwon: Page Number:
18 5 of41 3.1.3.16 l/2-OD C-3.03 , ODCM : Controls for RETS and REMP Programs 3.1.3.17 CR 02-06174, Track ing of Activities for Unit 1 RCS Zinc Addition Implementation. CA-014, Revise ODCM Proced ure l/2-0D C-2.01 (Tables 1.1-la and 1b) to include the addition of Zn-65 to the ODCM liquid source term.
3.1.3.18 CR 03-02466, RFA-Radiation Protection Efflue nt Contro l Provide Recom menda tion on Processing when Perfor ming Weekl y Sample of
[1LW-TK-7A/7B]. CA-02, Revise ODCM Proced ure l/2-ODC-2.01 (Attachment D) to show the liquid waste flow path cross-connect betwe en Unit 1 and Unit 2.
3.1.3.19 CR 05-03306, Incorporated Improved Techn ical Specifications (ITS).
3.1.3.20 CR 05-03854, ODCM Figure for Liquid Efflue nt Releas e Points Need Updat ed.
CA-01, revise ODCM procedure l/2-ODC-2.01 (ODCM: Liquid Efflue nts)
Attachment D, Figure 1.4-3 to incorporate a modif ied version of Plant Drawi ng No. 8700-RM-27F.
3.1.32 1 Unit 1 Technical Specification Amendment No. 275 (LAR lA-30 2) to Licens e No. DPR-66. This amendment to the Unit I licens e was approved by the NRC on July 19, 2006.
3.1.3.22 Vendo r Calcul ation Package No. 8700-UR(B)-223, Impac t of Atmos pheric Containment Conversion, Power Uprate, and Altern ative Source Terms on the Alarm Setpoints for the Radiation Monitors at Unit 1.
3.1.3.23 Engineering Chang e Package No. ECP-04-0440, Exten ded Power Uprate 3.1.3.24 CR 06-04908, Radia tion Monitor Alarm Setpoi nt Discrepancies. CA-03
- revise ODCM proced ure l/2-0D C-2.01 to update the alarm setpoints of [RM-l RW-1 00]
and [RM-l DA-10 0] for incorporation of the Exten ded Power Uprate per Unit 1 TS Amen dment No. 275.
3.1.3.25 CR 06-6476, Proced ure l/2-ODC-2.01 needs revise d for Plant Uprate
. CA-01 ;
revise ODCM proced ure 1/2-0D C-2.0l to update the alarm setpoints of
[2SWS-RQ101] for incorporation of the Exten ded Power Update at Unit 2 (ECP-04-0441) per Unit 2 TS Amendment No. 156.
3.1.32 6 CR 05-00004-15, CR05- 00004 -l 7 and SAP Order 200197646-0010 to revise l/2-0D C-2.0 1. Add the Coolant Recovery Tanks [1BR-TK-4A/4B]
as Liquid Waste Tanks to Sectio n 8.4 description and Attach ment D Figures 1.4-1 and 1.4-2.
Add a defaul t 2-tank volume recirculation time of 45.7 hrs for the Coola nt Recovery Tanks [1BR-TK-4A/4B] to Attach ment B Table 1.2-la Add the Cesium Remo val Ion Exchangers [lBR- I-lA/1 B and 2BRS-IOE21A/21B
] to Section 8.4 descri ption and Attachment B Figures 1.4-1 and 1.4-2. Revise the recirculation times in Attachment B Table 1.2-1 a and 1.2-1 b to indica te the times for nomin al tank volum e and maximum tank volume.
Procedme Number:
Beaver Valley Power Station 1/2-0DC-2.0l
Title:
Unit Level OfU9C:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revimon: Pago Number:
1~ 6nf'.tl 3.1.3.27 SAP Order 200197646-0660. Revise 1/2-ODC-2.0l 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.
3.1.3.28 SAP Order 200197646-0810. Revise l/2-0DC-2.01 to incorporate alarm setpoints for all possible detector combinations for [RM-lDA-100]. Specifically, due to obsolescence of the original Model 843-30 and 843-32 detectors that were previously installed in [RM-lDA-100], the vendor has upgraded them to Model 843-30R and 843-32R detectors, which include upgraded efficiency data as well.
3 .1.3 .29 CR 10-86844 revises 1/2-0DC-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.
3.1.3.30 ECP 11-0049 and CR 2012-02583 implement changes to the design of the liquid waste system for Phase 2 of Coolant Recovery Project.
3.1.3.31 SAP Notification 600747531, Update l/2-0DC-2.01 for RM-lRW-100.
3.1.3.32 CR-2012-05875, Antimony-126 identified in the liquid waste system.
3.1.3.33 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.
3.1.3.34 CA 2012-15547-7, To address the extent of condition with potential gaps in Radiological Effluent Program, evaluate the need to place appropriate ODCM controls on various non-radiological tanks and sumps throughout the site.
3.1.3.35 Engineering Change Package (ECP) 12-0478, Liquid Waste Demin Project:
Installation of new Demineralizers in Solid Waste Building. ~"
3.1.3.36 Engineering Change Package (ECP) 19-0230, Remove Effluent Flow Path to the I"'
River and Abandon Radiation Monitor RM-lDA-100.
r-3.2 Commitments 3.2.1 Beaver Valley Technical Specifications: [TS] 5.5.2, Radioactive Effluent Controls Program.
Beaver Valley Power Station Procedure Number:
l/2-0DC -2.01
Title:
Unit Level OfU1e:
1/2 General Skill Reference ODCM: LIQUID EFFLU ENTS Revision: Page Number:
1~ 7 nf.:1~
4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculat ion supporting ODCM changes shall be doeun1ented, as appropriate, by a retrieva ble docume nt (e.g.; letter or calculat ion package) with an appropriate RTL number.
4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 Precautions 5.1.1 None 5.2 Limitations 5.2.1 In Section 8.1, Alarm Setpoints, of this procedu re effluent monitor setpoints for a conserv ative mix are based on the individu al unit's specific parameters, but effluent monitor setpoints for analysis prior to release permit use the total dilution flow availabl e
at the site.
5 .2.2 BV-1 and BV-2 utilize the concept of a shared liquid radioact ive waste system accordin g
to NUREG -0133. (3.1 3 .1) This permits the mixing of liquid radwast e for processing and allocating of dose due to release as defined in Section 8.4, Liquid Radwas te System.
5.2.3 A differen ce in alarm setpoint termino logy for the radiatio n monitor ing systems ofBV-1 and BV-2 is described as follows:
5.2.3.1 HIGH and HIGH-HIGH termino logy are used for BV-1 monitor s and ALERT and HIGH terminology is used for BV-2 monitors.
5.2.3.2 BV-1 alarm setpoint units are express ed as counts per minute (cpm) and BV-2 alarm setpoints units are expresse d as microcurie per millilite r (uCi/mL). The differen ce is due to BV-2 software which applies a convers ion factor to the raw data (cpm) to convert units to uCi/mL . Note that the uCi/mL presentation is technica lly correct only for the specific isotopic mix used in the determination of the conversion factors. Therefore, BV-2 setpoints determi ned on analysis prior to release will be correct for properly controll ing dose rate, but the indicated uCi/mL value may differ from the actual value.
Procedure Number:
Beaver Valley Power'Station l/2-0DC-2 .01
Title:
Unit Level OfUac:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revision: Page Nambcr:
lR R nf.d.~
5.2.4 This procedure also contains information that was previously contained in Section 5 of the previous BV-1 and 2 Offsite Dose Calculation Manual.
5.2.4.1 In regard to this, the site boundary for liquid effluents was included in this procedure.
5.2.4.2 The Site Boundary for Liquid Effluents is shown in A TIACHMEN T D Figure 5-1.
6.0 ACCEPTANCE CRITERIA 6.1 Changes to this procedure shall contain sufficient justificatio n 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.I.3.2) 6.1.1 Changes to this procedure shall be prepared in accordance with 1/2-ADM-0100, PROCEDU RE WRITER'S GUIDE (3.u.1 4) and 1/2-ADM-1 640, CONTROL OF THE OFFSITE DOSE CALCULA TION MANUAL . (3.i 3 .1 3) 6.1.2 Changes to this procedure shall be reviewed and approved in accordance with NOP-SS-30 01, PROCEDU RE REVIEW AND APPROVA L (3.1. 3.15) and 1/2-ADM-1640. (3.1 3 .1 3) 7.0 PREREQUISITES 7.1 None 8.0 PROCEDURE 8.1 Alarm Setpoints 8.1.1 BV-1 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIG H Alarm Setpoint (HHSP) to provide indication if the concentration of radionuclid es in the liquid effluent released from the site to unrestricted areas exceeds 10 times the Effluent Concentrations (ECs) specified in 10 CFR 20, Appendix B (20.1001-20.2402), Table 2, Column 2 for radionuclid es other than dissolved or entrained noble gases or exceeds a concentration of2E-4 uCi/mL for dissolved or entrained noble gases. (3.1.3.S)
The methodolo gy described in Section 8.1.1.2 is an alternative method to be used to determine the [RM-lLW- 104], LIQUID WASTE EFFLUEN T RADIATIO N MONITOR or
[RM-lLW- 116], LIQUID WASTE CONTAM INATED DRAINS RADIATIO N MONITOR
Beaver Valley Power Station Procedure Number:
1/2-0DC -2.01
Title:
Unit Level OfU11e:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revimon: Page Number:
lR 9nf.:11 monitor HI-ISP. The methodol ogy 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/mL and 7.33E-3 uCi/mL. This concentra tion is equivalen t to the respective HHSPs derived in Section 8.1.1.1 and allows for respectiv e tritium concentrations up to 4.26E+-O uCi/mL and 9.94-E+o uCi/mL. <3 .1.3 .8) 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-1 LIQUID MONITO R SETPOINTS cpm Above BackJ?;round Monitor CR HHSP HSP Liquid Waste Effluent Monitor RM-lLW -104 4.15E+5 ~ 4.15E+5 ~ 2.91E+5 (953-36E)
Laundry And Contamin ated RM-lLW -116 9.69E+5 ~ 9.69E+5 :5: 6.78E+5 Shower Drains Monitor (953-36E)
Compone nt Cooling/ RM-lRW -100 2.57E+4 ~ 1.90E+4 {I) ~ 1.33E+4 (I)
Recircula tion Spray Hx River (843-30)
Water Monitor Compone nt Cooling Hx River RM-lRW -101 9.03E+3 :5: 9.03E+3 ~ 6.32E+3 Water Monitor (843-30) I
<1> Calculation Package ERS-ATL-93-021 Revision 4, for detector efficiency at elevated river 13 8 temperatures. C3 * >
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.u.22) The setpoints for RM-lLW -104 and RM-lLW -116 are based on the following conditions:
- Source terms given in ATTACH MENT A Table 1.1-la These source terms (without Zn-65) have been generated from the GALE Compute r Code, as
. described in NUREG- 0017. (3.1 33>The inputs to GALE are given in l/2-0DC- 3.01 Appendix B. The Zn-65 source term was generated via Calculati on Package No.
ERS-ATL-93-021. (3.1 3 *8* 3.1 3 .17)
- -. Dilution water flow rate of22,800 gpm = (15,000 gpm BV-1 + 7,800 gpm BV-2).
- Discharg e flow rate prior to dilution of 35 gpm for the Liquid Waste Effluent Monitor (RM-lLW -104).
- Discharg e flow rate prior to dilution of 15 gpm for the Laundry and Contamin ated Shower Drains Monitor [RM-lLW -116].
Proceduro Number.
Beaver Valley Power Station l/2-0DC-2.01
Title:
Unit Level OfU90:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revis.ion* PageNwmer:
1~ 10of4~
The above setpoints for [RM-lLW-10 4] and [RM-lLW-11 6] can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows:
542F HHSP=- [1.1(1)-1]
f where:
HHSP = Monitor HIGH-HIGH Alarm Setpoint above background (ncpm).
542 = Most restrictive proportionali ty constant based on nominal flow conditions:
542 = 3.53E+5 ncpm x 35 gpm + 22,800 gpm [RM-lLW-10 4]
542 = 8.24E+5 ncpm x 15 gpm + 22,800 gpm [RM-lLW-11 6]
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 Radionuclide s The "mix" (radionuclide s 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 ATTACMEN T A Table 1.1-la.
- The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (Si) for each individual radionuclide in the liquid effluent was determined as follows:
[1.1(1)-2]
where:
Ai= Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from ATTACHME NT A Table 1.1-la.
Beaver Valley Power Station Proccdmc Number:
l/2-0DC-2.01 Tide: Unit Lcve!OfU e:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Rcvi&ion: Page, Number:
lR 11 nf A.l 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 (Ct) was determined by:
Ct= -=---
F [1.1(1)-3]
fL _fu_
iOECi 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 BV-1 + 7,800 gpm BV-2) f = Maximum acceptable discharge flow rate prior to dilution (gpm).
= 35 gpm for Liquid Waste Effluent Monitor [RM-lLW-104].
= 15 gpm for Laundry and Contaminated Shower Drains Monitor [RM-lLW-116].
OECi = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/mL) from ATTACHMENT A Table 1.1-la. 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 [l.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:
[l.1(1)-4]
Procedure Number:
Beaver Valley Power Station l/2-0DC- 2.01
Title:
Unit Lovc!OfU11e:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Pago Number:
18 12 nfd~
8.1.1.1.4 BV-1 Monitor Count Rate The calculate d monitor count rate (ncpm) above backgrou nd attnbuted to the radionucl ides; (CR) was determined by:
[1.1(1)-5]
where:
Bi= Detection efficiency of the monitor for radionuclide "i" (cpm/uCi/mL) from ATTACH MENT A Table 1.1-la. If not listed in Attachme nt A, then obtained from Calculation Package ERS-SFL 039. (3.t.l.4) 8.1.1.1.5 BV-1 Monitor HHSP The monitor HHSP above backgrou nd (ncpm) should be set at the CR value.
Since only one tank can be released at a time, adjustme nt of this value is not necessary to compensa te for release from more than one source.
8.1.1.2 BV-1 Setpoint Determination Based On Analysil Prior To Release The following method applies to liquid releases when determin ing the setpoint for the maximum acceptabl e discharge flow rate prior to dilution and the associated IIBSP Alarm Setpoint based on this flow rate for the [RM-lLW -104], LIQUID WASTE EFFLUE NT MONITO R and the [RM-lLW -116], LAUNDR Y AND CONTAMINATED SHOWER DRAINS MONITO R during all operational conditions.
The monitor alarm setpoint is set slightly above ( a factor of 1.25) the count rate that results from the concentra tion of gamma emitting radionucl ides 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 from activity concentration, the alarm setpoint will be proportio nally adjusted based upon the excess dilution factor provided.
Beav er Valley Powe r Station Procedure Number.
1/2-0DC -2.01 Titlc:
Unit Level OfUac:
1/2 General Skill Reference ODCM: LIQUID EFFLU ENTS Revision: Page Numbcc.
1R B of A.1.
8.1.1.2.1 BV-1 Maximu m Acceptable Dischar ge Flow Rate The maximu m acceptab le discharge flow rate (f) prior to dilution (gpm) is determin ed by:
f= F [1.1(1)-6]
1.251: Ci iOEC1 where:
F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdo wn (gpm).
The dilution water flow rate may include the combin ed cooling tower blowdo wn flow from both units exiting the discharg e structur e (but excludin g emergen cy outfall structur e flow) when simultan eous liquid discharges are administratively prohibit ed.
Ci = Radioactivity concentration of radionu clide "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 deviatio ns in the mixture of radionuclides which affect the monitor re$p0nse.
OEC1 = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/mL ) from ATTAC HMENT A Table 1.1-la. The OEC is set at 10 times the 10 CPR 20, Append ix B (20.100 1-20.24 02) Table 2, Col.
2 EC values.
8.1.1.2. 2 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above backgro und attribute d to the radionuclides, (CR) is determin ed by:
CR = 1.25 1: Ci Bi [1.1(1)-7]
1 where:
Bi = The detection efficiency of the monitor for radionuclide "i" (cpm/uC i/mL) from ATTAC HMENT A Table 1.1-la If not listed in Attachm ent A, then obtained from Calcula tion Package ERS-SF L-92-03 9. (3.1.1.4>
1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor respons e.
Proccdorc Number:
Beaver Valley Power Station l/2-0DC-2. 01 Trtle: Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number:
18 14 nf A.~
8.1.1.2.3 BV-1 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:
IIlISP = CR f [1.1(1)-8]
f where:
IIlISP = Monitor IIlISP 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 off may be due to pump limitations or administrative selection.
8.1.2 BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor IITGH Alarm Setpoint (HSP) that indicates if the concentration ofradionuc lides 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 3 .8)
The methodology described in Section 8.1.2.2 is an alternative method to be used to determine the [2SGC-RQ 100], LIQUID WASTE EFFLUENT RADIATION 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 l. l 4E-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. l 6E+o uCi/mL. The setpoint was obtained by use of a conversion factor of 5.61E-9 uCi/mI.lcpm determined for the nuclide mix. (3.I.3. 8)
Beave r Valley Power Station Procedure Number:
1/2-0DC-2.01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Page Number:
18 15 nf .d.1 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 MONITO R SETPOJNTS uCi/mL Above Backgrou nd Monitor DV HSP ASP Liquid Waste Effluent 2SGC-RQ100 l.14E-3 ~ 1.14E-3 :5: 7.99E-4 Monitor Service Water Monitor 2SWS-RQ101 4.30E-5 ~ 4.30E-5 :5: 3.0lE-5 Service Water Monitor 2SWS-RQ102 4.30E-5 ~ 4.30E-5 :5: 3.0lE-5 The setpoint for [2SGC-RQ100] is based on the following conditions, however, the setpoint bases for [2SWS-RQ 101] and [2SWS-RQ 102] can be found in Calculation Package ERS-ATL-93-021. (3.1 3 .8>
- Source terms given in ATTACH MENT A Table 1.1-1 b. These source terms (without Zn-65) have been generated by using models and input similar to NUREG-0017. The inputs are given in l/2-0DC- 3.01. The Zn-65 source term was generated via Calculation Package No. ERS-ATL-93-021. (3. 13 .s, 3*13-17)
- Dilution water flow rate of22,800 gpm = (15,000 gpm BV-1 + 7,800 gpm BV-2).
- Discharg e flow rate prior to dilution of 80 gpm for the Liquid Waste Effluent Monitor [2SGC-RQ 100].
- A software conversion factor of 5.61E-9 uCi/mUc pm associated with Liquid Waste Effluent Monitor [2SGC-RQ 100]. (3.u.8)
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 = 4.00E-6 F [1.1(2)-1]
,f where:
HSP = HSP (uCi/mL) above background.
4.00E-6 = Proportionality constant based on nominal flow conditions:
4.00E-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).
Proccdurc Number:
Beaver Valley Power Station l/2-0DC- 2.01 Title*
Unit: Lovo!OfUac:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Pago Number:
18 16 n-f 41 8.1.2.1.1 BV-2 Mix Radionuclides The "mix" (radionuclides and composit ion) of the liquid effluent was determin ed as follows:
- The liquid source terms that are represent ative of the "mix" of the liquid effluent were determined. Liquid source terms are the radioactiv ity levels of the radionuclides in the effluent from ATTACH MENT A Table 1.1-lb.
- The fraction of the total radioacti vity in the liquid effluent comprise d by radionuclide "i" (Si) for each individua l radionuclide in the liquid effluent was determin ed as follows:
Si= Ai [1.1(2)-2]
i where:
Ai =Annual release of radionucl ide "i" (Ci/yr) in the liquid effluent from ATTACH MENT A Table 1.1-lb.
8.1.2.1.2 BV-2 Maximum Acceptable Concentr ation (All Radionuclides)
The maximum acceptable total radioacti vity concentration (uCi/mL) of all radionuclides in the liquid effluent prior to dilution (Ct) was determin ed by:
Ct=__E_ [1.1(2)-3]
fLi~
OECi where:
F = Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdow n Rate (not including release out through the Emergen cy 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 concentra tion limit for radionuclide "i" (uCi/mL) from ATTACH MENT A Table 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.
S1 = The fraction of total radioacti vity attributed to radionuclide "i", from Equation [l.1(2)-2] .
Beaver Valley Power Station Procedure Number.
1/2-0DC -2.01 Unit LevclOfUsc:
1/2 General Skill Reference ODCM: LIQUID EFFLU ENTS Rcvmon: PageNumber:
lR 17 nf A.~
8.1.2.1.3 BV-2 Maximu m Accepta ble Concent ration (Individ ual Radionu clide) l The maximu m acceptab le radioact ivity concent ration (uCi/mL ) of radionu clide "i" in the liquid effluent prior to dilution (Ci) was determi ned by:
[l.1(2)-4 ]
8.1.2.1.4 BV-2 Monitor Display Value The calculat ed monitor Display Value (uCi/mL ) above backgro und attribute d to the radionuclides; (DV), was determi ned by:
DV = 5.61E-9 Li Ci E1 [1.1(2)- 5]
where:
5.61E-9 = Convers ion factor (uCi/mU cpm), an average determi ned for the source term mix.
Bi = Detectio n efficien cy of the monitor for radionu clide "i" (cpm/uC i/mL) from ATTAC HMENT A Table 1.1-lb. If not listed there, from Calcula tion Package ERS-SF L-86-02 6. (3.1.2.2) 8.1.2.1.5 BV-2 Monitor HSP The monitor HIGH Alarm Setpoin t above backgro und (uCi/mL ) should be set at the DV value.
8.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release The followin g method applies to liquid releases when determi ning the setpoint for the maximu m acceptab le discharge flow rate prior to dilution and the associat ed HIGH Alarm Setpoin t based on this flow rate for the Liquid Waste Effluen t Monitor (2SGC- RQ 100) during all operational conditio ns.
The monitor alarm setpoint is set slightly above ( a factor of 1.25) the concent ration reading that results from. the concent ration of gamma emitting radionu clides in order to avoid spurious alarms. To compen sate for this increase in the monitor alarm setpoint , the allowab le discharge flow rate is reduced by the same factor.
When the discharg e flow rate is limited by the radwast e discharg e pump rate capacity or by adminis trative selectio n rather than the allowab le flow rate determi ned from activity concentration, the alarm setpoint will be proporti onally adjusted based upon the excess dilution factor provided .
Procedure Number.
Beaver Valley Power Station 1/2-0DC-2 .01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Rcviaion: Page Number:
lR lR of.:1.~
8.1.2.2.1 BV-2 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (t) prior to dilution (gpm) is determined by:
f= F [1.1(2)-6]
1.25 ~ Ci 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 simultaneo us liquid discharges from both plants are administrat ively prohibited.
Ci = Radioactiv ity concentrati on of radionuclid e "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 radionuclid es which affect the monitor response.
OECi = The ODCM liquid effluent concentrati on limit for radionuclid e "i" (uCi/mL) from Table 1.1-lb. The OEC is set at 10 times the 10 CFR 20, Appendix B (20.1001-2 0.2402) ATTACHM ENT A Table 2, Col. 2 EC values.
Beaver Valley Powe r Station ~Num ber:
l/2-0DC -2.01
Title:
Unit Level OfUac:
1/2 General Skill Referenc e ODCM: LIQUID EFFLUENTS Revision: Page Number:
lR 19 of 4".\
8.1.2.2.2 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/mL) above backgro und attributed to the radionuclides; (DV) is determined by:
DV = (1.25) (5.61E-9) Li Ci Ei [1.1(2)-7]
where:
Ei = The detectio n efficiency of the monitor for radionuclide "i" (cpm/uC i/mL) from ATTAC HMENT A Table I.I-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 = Convers ion factor (uCi/mLJcpm), 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 provide d as defined in the following equation:
HSP=D Vf [1.1(2)-8]
f where:
HSP = HSP above backgro und DV = Calculated monitor concentration reading (uCi/mL) from equation
[I.I (2)-7].
F = Maximu m acceptable discharge flow rate prior to dilution determined by equation [1.1(2)-6].
f = Actual maximu m discharge flow rate to be maintai ned for the discharge. The reduced value off may be due to pump limitations or administrative selection.
Procedure Number:
Beaver Valley Power Station l/2-0DC-2 .01
Title:
Unit Level OfUiO:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revision: Page Number:
18 'JO of.41 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-Releas e The radioactivi ty content of each batch release will be determined prior to release in accordance with l/2-ODC-3 .03, Table 4.11-1. In order to assure representat ive samples, at least two (2) tank volumes of entrained fluid from each tank to be discharged shall be recirculated. To meet this requiremen t tank recirculatio n time is calculated using actual tank volumes and recirculatio n 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 radionuclid es in the batch release, determined in accordance with l/2-0DC-3 .03, Table 4.11-1, is divided by the minimum dilution flow to obtain the concentrati on at the unrestricted area. This calculation is shown in the following equation:
ConCi= CiR [1.2-1]
MDF where:
Conci = Concentrat ion of radionuclid e "i" at the unrestricted area (uCi/mL).
Ci = Concentrat ion of radionuclid e "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 simultaneo us liquid discharges are administrat ively prohibited) .
The projected concentrati ons in the unrestricte d area are compared to the OECs.
Before a release is authorized, Equation [1.2-2] must be satisfied.
~ (ConcJOEC i) < 1 [1.2-2]
where:
OECt = The ODCM effluent concentrati on limit of radionuclid e "i" (uCi/mL) from ATTACHM ENT 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. (3.1.3.I0)
Beaver Valley Power Station Procedure Number:
l/2-0DC- 2.01
Title:
Unit: Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Page Number:
18 21 nfd1 8.2.1.2 Post-Rele ase Followin g release from the batch tank, the Post Dose Correctio n Factor will be calculate d in the following manner:
PDCF = {YAt)l(DFA)
[1.2-3]
(V1)/(DFI) where:
PCDF = Post Dose Correction Factor.
V At = Actual Volume of tank released (gal).
DFA = Actual Dilution Flow during release (gpm).
V1 = Initial Volume authorized for release (gal).
DFI = Initial Dilution Flow authorized for release (gpm).
The concentra tion of each radionuclide following release from the batch tank will be calculated in the unrestricted area in the following manner when the Post Dose Correctio n 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 concentra tion in the unrestricted area. This calculation is shown in the following equation:
[1.2-4]
where:
Conea = 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-mix ed tank at essentially a uniform rate, the difference between average and peak concentra tion within any discharge period is minimal.
Ca = Concentration of radionuclide "i" (uCi/mL) in batch release chning time period k.
V tk = Volume of Tank released during time period k (gal).
ADFk = Actual volume of Dilution Flow during the time period of release k (gal).
Procedure Number:
Beaver Valley Power Station l/2-0DC-2 .01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS R.eviaion: PaaoNumber.
18 ?? nf A.1 To show compliance with ODCM CONTROL 3 .11.1.1, the following relationshi p must be satisfied:
Li(ConCu.:/OECi) :-:; 1 [1.2-5]
8.2.2 Continuous Releases Continuous releases of liquid effluents do not normally occur at BV-1 or BV-2. When they do occur, the concentrati on of various radionuclides in the unrestricted area would be calculated using Equation [1.2-1] with Ci.k, the concentrati on 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 Lim.its {ODCM CONTRO LS 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. (3.1.3.I) This permits mixing of the liquid radwaste for processing. Since the resulting effluent release cannot accurately be attributed to a specific reactor unit, the treated effluent releases are allocated as defined below.
8.3.l Cumulation Of Doses (ODCM CONTRO L 3.11.1.2)
The dose contributio n 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 contributio n will be calculated using the following equation:
D-r = UAF L Ai-r LmAtk Cik Fk [1.3-1]
I k=l where:
D-r = The cumulative dose commitme nt to the total body or any organ, -r, from the liquid effluents for the total time period m
LAtk (mrem) k=l Atic = The length of the kth release over which Cik 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 A~ from any liquid release.
At-r = The site related ingestion dose commitmen t factor to the total body or any organ
-r for each identified principal gamma and beta emitter (mrem-mL per hr-uCi) from ATTACHM ENT B Table 1.3-1.
Beav er Valley Power Station Procedure Number:
l/2-0DC -2.01
Title:
Unit: Level OfUae:
1/2 General Skill Reference ODCM: LIQUID EFFLU ENTS Revision: Page Number:
lR ?'.:I. of .1'.:l m = Number of releases contribu ting to the cumulat ive dose, Dt.
UAF = Unit allocatio n factor. Provide s apportio nment of dose between BV-1 and BV-2. Normall y set at 0.5 for each unit. (Must total to :S 1.0).
Fk = The near :field average dilution factor for Cik during any liquid effluent release.
Defined as the ratio of the average undilute d liquid waste flow to the product of the average flow from the site discharg e structure during the report period to unrestri cted receivin g waters, times 3 (3 is the site specific applicab le factor for the mixing effect of the BV-1 and BV-2 discharg e structur e). Since all liquid release pathway s lead to the river, it can be assumed that all liquid waste flow mixes with flow from the site discharg e structure and can include the factor of 3 in the near field average dilution factor.
= Waste Flow (3) (Dilutio n Water Flow)
The site specific applicab le factor of 3 results in a conservative estimate of the near field dilution factor based upon Regulat ory Guide 1.113 (3.1. 3.4) methodo logy and is a factor of 10 below the limit specifie d in NUREG -0133, Section 4.3. (3.1 3 .1)
The dose factor Ai-r was calculated for an adult for each isotope using the followin g equation from NUREG -0133 <3 .1 3 .1>.
Ai-t = l.14E5 (730/Dw + 21BF1)DFi-r [1.3-2]
where:
730 = Adult water consum ption 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 consum ption.
21 = Adult fish consum ption {kg/yr).
BF1 = Bioaccu mulatio n factor for radionu clide "i" in fish from Table A-1 of Regulat ory Guide 1.109<3-13 5> (pCi/kg per pCi/1). Howeve r, if data was not availabl e from that referenc e, it was obtained from Table 6 of UCRL-5 0564. (3.1 3 .1 2>
The bioaccu mulatio n factor for niobium (300 pCi/kg per pCi/1) was not obtained from either of the above referenc es noted. It was obtained from IAEA Safety Series No. 57. Justifica tion for use of this value is docume nted in Append ix A to Calcula tion Package No. ERS-AT L-83-02 7. (3.I. 3.6)
Procedure Number.
Beave r Valley Power Station 1/2-ODC-2.01
Title:
Unit Level OfUsc:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number:
1R 'M. nf4~
DF1-r = Dose conversion factor for radionuclide "i" for adults for a particular organ 't (mrem/pCi) from Table E-11 of Regulatory Guide 1.109, (3.1 3 .s) ERS-LMR.-
15-006, (3.1 3 .9) or NUREG-0172. (3.1. 3.1 1>
A table of Att 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-1 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 CON1ROL 3.11.1.2 ~ follows:
For the calendar quarter, D-r < 1.5 mrem total body [1.3-3]
D-r < 5 mrem any organ [1.3-4]
For the calendar year, D-r < 3 mrem total body [1.3-5]
D-r < 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 l/2-ODC-3.03 is required. (3.1 3 .16) 8.3.2 Projection Of Doses (ODCM CONTR OL 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:
Beave r Valley Power Station Procedure Number.
l/2-0DC- 2.01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Page Number:
18 ?A:i nf A.~
When including pre-relea se data, A+B]
D 31 = [ - T- 31+C [13-7]
When not including pre-relea se data,
[13-8]
where:
DJ1 = Projected 31 day dose (mrem).
A = Cumulati ve 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 Radwast e System The liquid radwaste system has the capability to control, collect, process, store, recycle, and ,
dispose of liquid radioactiv e waste generated as a result of plant operations, including anticipate d operation al occurrenc es. This system also uses some of the compone nts of the steam generator blowdow n system for processin g.
Simplifie d flow diagrams of the liquid radwaste systems for BV-1 and BV-2 are provided as ATTACH MENT C Figures 1.4-1 and 1.4-2 respectively. A diagram showing the liquid effluent release points is provided as ATTACH MENT C Figure 1.4-3. A diagram of the site boundary for liquid effluents is provided as ATTACH MENT 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 discharge d from either BV-1 or BV-2.
8.4.1 BV-1 Liquid Radwut e System Components 8.4.1.1 [lBR-I-lA /B], CESIUM REMOV AL ION EXCHAN GERS There are two (2) of these ion exchangers, each has a capacity of thirty-fiv e (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/B], COOLAN T RECOVE RY TANKS There are two (2) of these tanks, each tank has a nominal capacity of 195,000 gallons (maximu m 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-aerat ed drains that were processed through the [lBR-I-
Procedun, Number:
Beaver Valley Power Station l/2-0DC- 2.01
Title:
Unit Level OfUse:
1/2 General Skill Reference ODCM:L lQUIDE FFLUEN TS Rc.Miion: Pago Number:
18 ?£. of .d.1.
lA/B], CESIUM REMOV AL ION EXCHAN GERS from both Unit 1 and Unit 2.
These tanks can also receive unproces sed liquid wastes from either Unit 1 or Unit 2 liquid waste systems. Normally , one (1) tank receives liquid waste while the other tank is placed on recircula tion through the deminera lizer until the radioacti vity concentration is acceptabl e for discharge. A minimum of two (2) tank volumes must be recirculated prior to sampling for discharge permit preparation.
8.4.1.3 [1LW-TK-2AIB], HIGH LEVEL WASTE DRAIN TANKS There are two (2) of these tanks, each tank has a nominal capacity of 5,000 gallons (maximu m capacity = 4,899 gallons). They are located on the northwes t wall of the Auxiliary Building ( elevation 735'). They receive liquid wastes from the vent and drain system.
8.4.1.4 [1LW-TK -3A/B], LOW LEVEL WASTE DRAIN TANKS There are two (2) of these tanks, each tank has a nominal capacity of2,000 gallons (maximu m capacity = 1,998 gallons). They are located in the northwes t comer of the Auxiliary Building ( elevation 7351. They receive liquid wastes from the vent and drain system and can be transferre d directly to [1BR-TK.-4A/B], COOLAN T RECOVE RY TANKS. Although not normally used, these tanks can also be utilized to discharge processed or unproces sed liquid wastes. A minimum of two (2) tank volumes must be recircula ted prior to sampling for discharge permit preparati on.
8.4.1.5 [lLW-FL -7], LIQUID WASTE PRE-CO NDffiON ING FILTER A pre-cond itioning filter with a fifty (50) is designed to clean liquid waste water of particulate and dissolved radioactiv e contaminants that is stored in [1LW-TK -2A/B],
HIGH LEVEL WASTE DRAIN TANKS; [1LW-TK .-3A/B], WWLEV EL WASTE DRAIN TANKS; and [1BR-TK -4A/B], COOLAN T RECOVE RY TANKS. The pre-condi tioning filter can be charged with varying grades of activated charcoal (carbon) intended for removal ofradionu clides 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 Solid Waste Building (elevation 735'-6").
8.4.1.6 [lLW-I-3 ], LIQUID WASTE DEMINE RALIZE R There are two (2) deminera lizer 36" diameter vessels [lLW-I-3 -1, lLW-I 2] each with a capacity of thirty (30) cubic feet and two (2) demineralizer 24" diameter vessels [lLW-I-3 -3, lLW-I 4] each with a capacity of fifteen (15) cubic feet The demineralizers are designed to clean liquid waste water of particulate and dissolved radioactive contamin ants and pre-cond itioned by [lLW-FL -7]. The primary ion exchange occurs in [lLW-3-3 , lLW-I 4] exchange vessels. These vessels are located at the end of the process train to maximize the cleaning effect of the media
[lLW-I-3 -1, lLW-I 2] "accumul ator" vessels are placed at the front of the influent liquid waste deminera lizer line. These vessels are used as ion exchange process vessels, however they are normally used for holding partially depleted resin sluiced
Beaver Valley Power Station Procedure Number:
l/2-0DC- 2.01
Title:
Unit Lewi Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS R.evwon: Page Number:
lR 27 nf _.:11 in from the primary ion exchangers [ILW-I-3 -3, ILW-I 4]. Each of the deminera lizer vessels may be charged with different resins for effective removal of chemical and radioactive contamin ants. Resin selection and sequence may be changed dependen t upon site liquid waste processing needs. This deminera lizer is located in the Solid Waste Building (elevation 735'-6").
8.4.1.7 Liquid Waste Evaporat or An evaporato r was originally designed to process liquid waste at Unit 1 with a capacity of six (6) gpm. However , this evaporator was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste. SINCE the evaporato r is no longer in-use, TIIEN it is not shown on Figure 1.4-1 in ATTACH MENT C.
8.4.1.8 [1LW-TK.-7A/B], STEAM GENERA TOR DRAIN TANKS There are two (2) of these tanks, each tank has a nominal capacity of 34,500 gallons I
(maximu m capacity= 35,800 gallons). They are located in the Fuel Pool Leakage Monitori ng Room ( elevation 735l 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 completi on of filling operation, the tank is placed on recirculat ion through the deminera lizer until the radioactivity concentra tion is acceptabl e for discharge. A minimum of two (2) tank volumes must be recirculated prior to sampling for discharge permit preparation.
8.4.1.9 [RM-lLW -104], LIQUID WASTE DISCHA RGE RADIAT ION MONITO R An off-line gamma scintillator radiation monitor continuou sly analyzes liquid waste as it is being discharged. The normal rate of discharge through this radiation monitor from [1LW-TK.-3A/B], LOW LEVEL WASTE TANK.D RAIN TANKS and [lLW-TK.-7A/B] is less than thirty-five (35) gpm. The normal rate of discharge through this radiation monitor from [1BR-TK.-4A/B], COOLAN T RECOVE RY TANKS is less than 50 gpm. The high alarm on this radiation monitor has a setpoint that would
_ indicate liquid waste discharges that are approaching OEC limits. If a high high alarm is received, liquid waste discharge is automatically terminate d by closing the discharge line isolation valve.
8.4.1.10 [lLW-FL -8], RAD WASTE REVERS E OSMOSI S (RWRO) PRE-FIL TER A pleated paper mechanic al pre-filter upstream of [lLW-RW RO-1], RAD WASTE REVERS E OSMOSI S SKID is designed to prevent fouling of the system by buildup of suspende d solids in the reverse osmosis membranes. The shielded pleated-p aper filter is sized to filter particulat e down to 0.3 microns. The filter is contained within a lockable, shielded cover that allows access for filter replacem ent. This filter is located in the Solid Waste Building (elevation 735'-6").
Procedure Number:
Beaver Valley Power Station 1/2-0DC-2 .01
Title:
Unit Level OfUse:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revision: Page Number.
lR ?~ nf A.~
8.4.1.11 [ILW-RWR O-1], RAD WASTE REVERSE OSMOSIS SKID adds a physical membrane barrier to the chemical ion exchange system used in the current liquid waste deminerali zer system. This replaceable membrane barrier prevents radwaste particles that were not captured during the ion exchange process. [ILW-RWR O-1] does not capture the particles, but instead produces a reject stream separate from the permeate stream. The [ILW-RWR O-1] accepts the effluent stream of the demineralizer system [lLW-1-3], LIQUID WASTE DEMINER ALIZER and is designed to allow boron and silica particles to pass through while rejecting others such as antimony. If antimony is present in the effluent stream it is separated and is sent to [ILW-I-3-5 ], Antimony Vessel charged with antimony selective resin.
The antimony vessel removes the isotope from the reject stream prior to discharge back to the [IBR-TK-4 A/B], COOLANT RECOVER Y TANK being processed from. This skid is located in the Solid Waste Building (elevation 735'-6").
8.4.1.12 [ILW-I-3-5 ], ANTIMON Y VESSEL
[ILW-I-3-5 ], ANTIMON Y VESSEL is a two (2) cubic foot ion exchange vessel placed downstream of the [lLW-RWR O-1], RAD WASTE REVERSE OSMOSIS SKID. This vessel removes antimony isotopes from the reject stream of the [ILW-I-3-5] prior to discharge back to the [1BR-TK-4 A/B], COOLANT RECOVER Y TANK. being processed from. This skid is located in the Solid Waste Building (elevation 735'-6").
8.4.1.13 [ILW-I-3-6 ], POLISHIN G VESSEL
[ILW-I-3-6 ], POLISHIN G VESSEL is a fifteen (15) cubic foot ion exchange vessel placed downstream of the [lLW-RWR O-1], RAD WASTE REVERSE OSMOSIS SKID. This skid is located in the Solid Waste Building (elevation 735'-6").
8.4.1.14 Sample Sinks The sample sinks allow sampling at both influent and effluent vessel streams. In addition, the sinks include gauges that indicate the pressure at each sample point.
One sample sink is located locally (Solid Waste Building- elevation 735'-6") to the system and allows for sampling from eight (8) individual points within the system.
A second sample sink is remotely located and contains four (4) sampling points (Primary Auxiliary Building - elevation 768'-7" along the east wall). A sample sink is also included on the [lLW-RWR O-1], RAD WASTE REVERSE OSMOSIS (RWRO) SKID to provide sample points from within the skid itself.
Beaver Valley Power Station Procedure Number:
l/2-0DC- 2.01 Trtle: Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Page Nmnbcr:
18 29 nf 4-:\
8.4.2 BV-1 Laundry and Contaminated Shower Drain System Components 8.4.2.1 [1LW-TK-6AIB], LAUNDR Y AND CONTAM INATED SHOWER DRAIN TANKS There are two (2) of these tanks, each has a nominal capacity of 1,200 gallons (maximu m capacity = 1,303 gallons). They are located in the northwest comer of the Auxiliary Building (elevation 722'). They receive laundry and contamin ated shower drains waste from the Service Building. These tanks can also receive mop water waste and other low-level contaminated 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 compoun ds that will deplete a resin bed. Upon completion of filling operation, the tank must be recirculated n minimum of two (2) tank volumes prior to sampling for discharge permit preparation. '
8.4.2.2 [RM-lLW -116], LAUNDR Y AND CONTAM INATED SHOWE R DRAINS TANK DISCHA RGE RADIAT ION MONITO R An off-line gamma scintillator radiation monitor continuo usly analyzes laundry and contaminat.ed shower drains waste as it is being discharge d. The normal rate of discharge through this radiation monitor from [1LW-TK -6A/B], LAUNDR Y AND CONTAM INATED SHOWE R DRAIN is less than fifteen (15) gpm. The high alarm on this radiation monitor has a setpoint that would indicate liquid waste 1 discharges are approaching OEC limits. If a high high alarm is received, liquid waste discharge is automatically terminated by closing the discharge line isolation valve.
8.4.3 BV-2 Liquid Radwaste System Components 8.4.3.1 [2BRS-IOE21A/B], CESIUM REMOV AL ION EXCHAN GERS There are two (2) of these ion exchangers, each has a capacity of thirty-five (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-TK21A/B], WASTE DRAIN TANKS There are two (2) of these tanks, each tank has a nominal capacity of 10,000 gallons (maximu m capacity = 10,184 gallons). They are located in the northeast comer 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 (2) tank volumes must be recirculated prior to sampling for discharge permit preparation.
Procedure Number:
Beaver Valley Power Station 1/2-0DC-2 .0 I
Title:
Unlt Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revhion: Page Number:
lR 10 ofA.1 8.4.3.3 [2SGC-IOE 21A/BSTE AM GENERAT OR BLOWDO WN CLEANUP ION EXCHANG ERS The main purpose of the ion exchangers is to clean liquid waste water of particulate and dissolved radioactive contaminan ts 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 (2) evaporators were originally designed to process liquid waste at Unit 2 with a cap~ty of twenty (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 inATTAC IIMENTC .
8.4.3.5 [2SGC-TK 23A/B], STEAM GENERAT OR BLOWDO WN TEST TANKS There are two (2) 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 755l They receive liquid waste that has been processed through the cleanup ion exchangers. Upon completion of filling operation, the tank is placed on recirculatio n through the deminerali zer until the radioactivity concentrati on is acceptable for discharge. A minim1un of two (2) tank volumes must be recirculate d prior to sampling for discharge permit preparation.
8.4.3.6 [2SGC-TK 21A/B], STEAM GENERAT OR BLOWDO WN HOLD TANKS There are two (2) 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 concentrati on of the steam generator blowdown test tank is not acceptable for discharge. These tanks can also receive liquid wastes from Unit I.
The contents of this tank may be drained or processed through the Unit I or Unit 2 Liquid Radwaste Treatment System until the radioactivity concentrati on is acceptable for discharge. A minim11m of two (2) tank volumes must be recirculate d prior to sampling for discharge permit preparation.
8.4.3.7 [2SGC-RQ I 00], LIQUID WASTE EFFLUEN T MONITOR A off-line gamma scintillator radiation monitor continuous ly analyzes liquid waste as it is being discharged. The normal rate of discharge through this radiation monitor is less than eighty-five (85) gpm. The alert alarm on this radiation monitor has a setpoint that would indicate liquid waste discharges are approachin g OEC limits. If a high alarm is received, liquid waste discharge is automatica lly terminated by closing the discharge line isolation valve.
Beaver Valley Power Station Procedure Number:
l/2-ODC- 2.01 Tide:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: PageNwnber:
18 ~1 of 4~
8.4.4 BV-1/2 Miscellaneous Sumps 8.4.4.1 Unit 1 Chemica l Waste Sump This sump has an approxim ate capacity of 16,755 gallons and the associate d trenches add an additiona l volume of approxim ately 5,140 gallons. The waste in this sump is not processed through any liquid waste deminera lizer for cleanup.
This sump cannot be complete ly isolated and does not have any radiation monitors. The sump discharges to Unit 1 Liquid Waste Line that discharge s to the Unit 1 Cooling Tower Blowdow n Line.
The Chemica l Waste Sump typically does not receive radiologi cal liquid waste.
When primary to secondar y leakage is greater than 0.1 gpm (142 gpd) releases of radioacti ve material from this sump are considere d to be continuou s liquid effluent discharge as specified in ODCM Control 3.11.1.1. When the Turbine Building Sump concentra tion exceeds I OEC, the Chemica l Waste Sump accepts flow from the Turbine Building Sump(s).
Prior to discharge the Chemical Waste Sump is sampled. Individua l liquid effluent batch discharge permits are not required ifno Licensed Radioact ive Material (LRM) is present and the discharge of tritium is accounte d for with a monthly secondar y diffusion permit If LRM is detected in the Chemica l Waste Sump, then a special permit is required. Upon completio n of filling operation , the sump must be recirculat ed a minimum of two (2) volumes prior to sampling for batch discharge permit preparation.
During normal plant operation, this sump may be used for the treatment and disposal of radiologi cal materials for various projects at the discretion of site managem ent When Licensed Radioact ive Material from a source other than a Turbine Building drain of secondary water is added to the sump, the sump may be discharge d using batch release methods if concentra tion and dose limits are maintaine d.
Procedure Number:
Beaver Valley Power Station 1/2-0DC-2 .01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revision: Page Number:
18 '.:!.? nf' .d'.:1.
8.4.4.2 Unit2 Cable Vault Sump This sump has a capacity of 2,424 gallons, however the high level alarm will actuate at 1,500 gallons. This sump cannot be completely isolated and does not have any radiation monitors. The waste in this sump is not normally processed through a liquid waste demineraliz er for cleanup because the sump may contain contaminan ts that would deplete the resin bed The sump normally receives non-radiologica l liquid waste. It is used for the collection and release of non-contaminat ed water. The open pit design provides the potential for radiologica l materials to enter the sump due to its location in the Radiological Controlled Area thus requiring Offsite Dose Calculation Manual (ODCM) controls prior to discharge.
Prior to discharge the Cable Vault Sump is sampled. Licensed Radioactiv e Material entering the sump may be discharged using batch release methods if concentrati on and dose limits are maintained . Typically, tritium is accounted for in monthly pre-release batch liquid effluent discharge permit This sump discharges into the Unit 2 Catch Basin System at 2CB-4. Upon completion of filling operation, the sump must be recirculate d a. minimum of two (2) volumes prior to sampling for discharge permit preparation .
-END-
Bea ver Valley Power Station Proccdurc Number:
l/2-0D C-2.0 1 Trtlc:
Unit Level OfUao:
11? General Skill Reference ODCM: LIQUID EFFLUENTS Revmon: Page Number:
18 ~~ nf A.~
ATIA CIIM ENTA Page 1 of 4 LIQUID SOURCE TERMS TABLE 1.1-la BV-1 LIQUID SOURCE TERM Bi (4)
Ai (2) DETECTION ANNUAL RELEASE OECi (3) EFFICIENCY NUCL IDE (Ci) (uCi/mL) (cpm/uCi/mL)
Cr-51 l.3E-3 5E-3 1.35E+7 Mn-54 3.lE-4 3E-4 1.03E+8 Fe-55 1.6E-3 lE-3 6.36E-1 Fe-59 8.3E-4 lE-4 9.98E+7 Co-58 1.4E-2 2E-4 1.40E+8 Co-60 2.0E-3 3E-5 1.84E+8 Zn-65 (3.l.3.17) 2.69E-2 5E-5 5.10E+7 Np-239 1.4E-4 2E-4 8.01E+7 Br-83 2.5E-5 9E-3 l.65E+ 6 Br-84 2.7E-6 4E-3 l.01E+8 Br-85 2.8E-8 - 6.60E+6 Rb-86 7.5E-5 7E-5 8.30E+6 Sr-89 2.9E-4 8E-5 9.64E+3 Sr-90 l.lE-5 5E-6 (5)
Y-90 9.4E-6 7E-5 1.10E+2 Y-91m 8.7E-6 2E-2 1.10E+8 Y-91 5.7E-5 8E-5 2.42E+5 Y-93 7.4E-7 2E-4 1.55E+7 Zr-95 5.lE-5 2E-4 1.06E+8 Nb-95 5.2E-5 3E-4 l.06E+ 8 Sr-91 l.3E-5 2E-4 8.32E+7 Mo-99 l.lE-2 2E-4 2.91E+7 Tc-99m 1.lE-2 lE-2 l.18E+8 Ru-103 3.4E-5 3E-4 l.17E+ 8 Ru-106 1.0E-5 3E-5 2.74E+7 Rh-103m 3.4E-5 6E-2 (5)
Rh-106 Te-125m l.0E-5 2.5E-5
- 3.87E+7 2E-4 l.73E+ 5 Te-127m 2.6E-4 9E-5 l.69E+ 4 Te-127 2.7E-4 lE-3 l.58E+ 6 Te-129m 1.lE-3 7E-5 4.41E+6 Te-129 6.7E-4 4E-3 l.43E+ 7 I-130 1.2.E-4 2E-4 3.68E+8 Te-131m 1.6E-4 8E-5 1.80E+8 Te-131 3.0E-5 8E-4 1.43E+8 I-131 1.6E-1 lE-5 l.27E+ 8
Procedure Number:
Beaver Valley Power Station l/2-ODC-2.01
Title:
Unit: Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: PageNumber:
18 ~A. nf A.~
ATTACHMENT A Page 2 of 4 LIQUID SOURCE TERMS TABLE 1.1-la (continued)
BV-1 LIQUID SOURCE TERM Bi (4)
Ai (2) DETECTION ANNUAL RELEASE OECi (3) EFFICIENCY NUCLIDE (Ci) (uCi/mL) (cpm/uCi/mL)
Te-132 4.3E-3 9E-5 l.34E+8 I-132 4.9E-3 lE-3 3.16E+8 I-133 4.0E-2 7E-5 1.21E+8 I-134 8.0E-5 4E-3 2.99E+8 Cs-134 4.6E-2 9E-6 2.44E+8 I-135 4.3E-3 3E-4 l.29E+8 Cs-136 8.9E-3 6E-5 3.05E+8 Cs-137 3.3E-2 lE-5 9.40E+7 Ba-137m 3.lE-2 - 9.93E+7 Ba-140 l.lE-4 8E-5 5.05E+7 La-140 l.lE-4 9E-5 1.91E+8 Ce-141 5.lE-5 3E-4 6.72E+7 Ce-143 2.8E-6 2E-4 8.26E+7 Ce-144 3.2E-5 3E-5 l.36E+7 Pr-143 2.7E-5 2E-4 1.28E+o Pr-144 3.2E-5 6E-3 2.27E+6 H-3 5.50E+2 lE-2 (5)
TOTAL Ol 4.05E-1 (1)
Excluding Tritium and Entrained Noble Gases (2)
Source Term for (RM-ILW-10 4 andRM-ILW -116) from Stone and Webster Calculation Package UR(B)-160 (3.l 1.6)
(3)
ODCM Effluent Concentration Limit= 10 times the EC values of 10 CFR 20 (3.1.3 10l (4)
Detection Efficiency for (RM-ILW-10 4 and RM-ILW-11 6) from Calculation Package ERS-SFL-92 -039 (3.1.14)
(S)
Insignificant
Beaver Valley Power Station Procedorc Number:
l/2-0D C-2.01
Title:
Unit Level Of Use:
1n General Skill Reference ODCM: LIQUID EFFLUENTS Rcviaion: Page Number.
lR 15 nf41 ATTA CHME NT A 1 Page 3 of 4 LIQUID SOURCE TERMS TABLE 1.1-lb BV-2 LIQUID SOURCE TERM R (4)
Ai (2) DETE CTIO N ANNU AL RELEASE OECi (3) EFFICIENCY NUCLIDE (Ci) (uCi/mL) (cpm/uCi/mL)
Cr-51 1.00E-4 SE-3 2.01E+7 Mn-54 2.S0E-5 3E-4 l.27E+ 8 Fe-55 1.30E-4 lE-3 (5)
Fe-59 6.S0E-5 lE-4 1.26E+8 Co-58 l.lOE- 3 2E-4 l.82E+8 Co-60 l.60E- 4 3E-5 2.38E+8 Zn-65 (3.1.3.17) 5.lOE-2 SE-5 6.50E+7 Np-239 3.20E-5 2E-4 l.65E+8 Br-83 2.90E-5 9E-3 2.42E+6 Br-84 5.90E-9 4E-3 l.38E+8 Rb-86 3.70E-5 7E-5 l.04E+ 7 Sr-89 2.20E-5 SE-5 l.83E+ 4 Sr-90 8.S0E-7 SE-6 (5)
Sr-91 5.30E-6 2E-4 l.04E+8 Mo-99 2.30E-3 2E-4 4.47E+7 Tc-99m 2.I0E- 3 IE-2 l.40E+8 Te-125m l.90E- 6 2E-4 3.94E+5 Te-127m 2.l0E- 5 9E-5 l.26E+5 Te-127 2.S0E-5 IE-3 2.43E+6 Te-129m 8.20E-5 7E-5 6.53E+6 Te-129 5.30E-5 4E-3 l.96E+ 7 I-130 2.30E-4 2E-4 5.18E+8 Te-13 lm 5.20E-5 8E-5 2.85E+8 Te-131 9.40E-6 8E-4 l.88E+8 I-131 l.00E-1 IE-5 l.96E+8 Te-132 7.80E-4 9E-5 l.76E+8 I-132 2.30E-3 IE-3 4.22E+8 I-133 6.S0E-2 7E-5 1.73E+8 I-134 4.60E-6 4E-3 4.06E+8 Cs-134 3.00E-2 9E-6 3.25E+8 I-135 9.20E-3 3E-4 l.71E+8 Cs-136 3.90E-3 6E-5 4.28E+8 Cs-137 2.20E-2 IE-5 1.28E+8 Ba-137m Ba-140 2.I0E- 2 -- l.33E+8 9.30E-6 8E-5 7.50E+7 La-140 8.40E-6 9E-5 3.08E+8
Procedure Number.
Beaver Valley Power Station l/2-0DC-2 .01
Title:
Unit: Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: PageNumber:
lR ~fl nf A.~
ATTACHMENT A Page4 of4 LIQUID SOURCE TERMS TABLE 1.1-1 b (continued)
BV-2 LIQUID SOURCE TERM Bi (4)
Ai (2) DETECTION ANNUAL RELEASE OECi (3) EFFICIENCY NUCLIDE (Ci) (uCi/mL) (cpm/uCi/mL)
Y-9lm 3.60E-6 2E-2 l.59E+8 Y-91 4.40E-6 8E-5 3.55E+5 Y-93 3.00E-7 2E-4 2.03E+7 Zr-95 4.00E-6 2E-4 1.35E+8 Nb-95 4.00E-6 3E-4 l.33E+8 Ru-103 2.70E-6 3E-4 1.71E+8 Ru-106 8.20E-7 3E-5 (5)
Rh-103m 2.70E-6 6E-2 (5)
Rh-106 8.20E-7 - 5.65E+7 Ce-141 4.00E-6 3E-4 7.75E+7 Ce-143 8.60E-7 2E-4 1.20E+8 Ce-144 2.60E-6 3E-5 1.87E+7 Pr-143 2.30E-6 2E-4 1.63E+o Pr-144 2.60E-6 6E-3 3.40E+6 H-3 5.50E+2 lE-2 (5)
TOTAL(!) 2.40E-1
(!)
Excluding Tritium and Entrained Noble Gases (2)
Source Term for (2SGC-RQ I 00) from Computer Code LIQ IBB (3.I 2 3>
(3) ODCM Effluent Concentration Limit= 10 times the EC values of 10 CFR 20 <3-1310>
(4)
Detection Efficiency for (2SGC-RQIOO) from Calculation Package ERS-SFL-86-026(31.2.2)
(5)
Insignificant
Beave r Valley Power Station Procedurc Number:
1/2-0DC- 2.01 Titlc: Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revilion: Pago Number:
18 37 nf 4~
ATTACH MENT B Page 1 of3 INGESTION DOSE COMMIT MENT FACTOR S TABLE 1.3-1 Au VALVES FOR TIIE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/m.L)
NUCTIDE BONE I1VER T-BODY 1HYROID KIDNEY LUNG GI-ill H-3 O.OOEOO 270E-01 27CE-01 270E-01 270E-01 270E-01 270£.01 1>>7 l.43M2 3.24E-02 159E-02 O.OOEOO 3.42E-02 O.OOEOO 5.62EOO C-14 3.13E04 6.26E03 6.26E03 6.26E03 616E03 6.26803 626E03 Na-24 4.08E02 4.08E02 4.08E02 4.08E02 4.08E02 4.08E02 4.08E02 P-32 4.62E07 287E~ l.79EOS 0.OOEOO O.OOEOO 0.OOEOO 5.19E~
0-51 O.OOEOO 0.OOEOO 127EOO 7.62.BOl 281E-01 l.0JEOO 321E02 Mn-54 O.CXJEOO 438E03 8.35E02 O.OOEOO 130E03 0.OOEOO 1.34E04 Mn-56 O.OOEOO 1.10E02 1.95E01 0.OOEOO l.40E02 0.OOEOO 352E03 Fe-55 659£02 4.56E02 l.06E02 0.CXJEOO O.OOEOO 2.54E02 261E02 Fe-59 l.04E03 245E03 938E02 0.OOEOO 0.OOEOO 6.83E02 8.15E03 Co-57 O.OOEOO 210£01 3.50E01 0.OOEOO 0.OOEOO 0.OOEOO 533E02 Co-58 0.CXlEOO 8.95E01 201E02 0.OOEOO 0.CXlEOO 0.OOEOO l.81E03 Co-00 0.OOEOO 2.57E02 5.67E02 0.OOEOO O.CXJEOO 0.OOEOO 4.83E03 Ni-63 3.12E04 216E03 l.05E03 0.OOEOO 0.OOEOO 0.OOEOO 451E02
~ 127E02 l.65E01 751EOO 0.OOEOO 0.OOEOO 0.OOEOO 4.17E02 Cu-64 0.OOEOO l.OOE01 4.70EOO 0.CXJEOO 2.52E01 0.OOEOO 853E02 Zn-65 232E04 737E04 333E04 0.OOEOO 4.93E04 0.OOEOO 4.64E04 Zn-ff) 4.93E01 9.43E01 6.56EOO 0.OOEOO 6.13E01 O.OOEOO l.42E01 Se-75 0.OOEOO l.86E03 7.22E02 0.OOEOO 270E03 0.OOEOO 269E02 Br-83 O.OOEOO 0.OOEOO 4.04801 0.OOEOO 0.OOEOO 0.CXEOO 5.82E01 Br-84 0.OOEOO 0.OOEOO 524E01 0.OOEOO 0.OOEOO 0.OOEOO 4.11.E-04 Br-85 0.OOEOO 0.OOEOO 215EOO 0.OOEOO 0.OOEOO O.OOEOO 0.OOEOO Rb-86 0.OOEOO l.01E05 4.71E04 0.OOEOO 0.OOEOO 0.OOEOO 19JE04 Rb-88 0.OOEOO 290E02 1.54E02 0.OOEOO 0.OOEOO 0.OOEOO 4.(X)E.()(J Rb-89 0.OOEOO l.92E02 135E02 0.OOEOO 0.OOEOO 0.CXEOO l.12E-11 Sr-89 222E04 O.OOEOO 639£02 O.OOEOO 0.OOEOO 0.CXEOO 3.57E03 Sr-90 5.48E05 0.OOEOO 1.34E05 0.OOEOO 0.OOEOO 0.OOEOO 158E04 Sr-91 4.10E02 0.OOEOO l.65E01 0.CXJEOO 0.OOEOO O.OOEOO 1.95E03 Sr-92 155E02 0.OOEOO 6.72EOO 0.OOEOO 0.OOEOO O.OOEOO 3.08E03 Y-90 5.80E-01 0.OOEOO 155E-02 0.OOEOO O.OOEOO 0.OOEOO 6.15E03 Y-91.m 5.48E-03 0.OOEOO 212E-04 0.OOEOO O.OOEOO 0.OOEOO 1.61E-02 Y-91 850£00 0.OOEOO 2.27B-01 0.OOEOO 0.OOEOO 0.<XEOO 4.68E03 Y-92 5.OCJE-02 0.OOEOO l.49E-03 0.OOEOO 0.00EOO 0.CXlEOO 8.92E02
Procedure Number:
Beaver Valley Power Station 1/2-0DC-2.01
Title:
Unit: Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUEN TS Revision: Page Number.
lR 1Rof41 AITACHM ENTB Page 2 of3 INGESTIO N DOSE COMMITM ENT FACTORS An VALVES FOR TIIE ADULT FOR TIIE BEAVER VALLEY SITE (mrem/hr per uCi/mL)
NUC1IDE BONE I.1VHl T-BODY TIIYR.OID KIDNEY WNG GI-III Y-93 l.62E-Ol O.OOEOO 4.46E-03 O.OOEOO O.OOEOO O.OOEOO 5.12E03 Zr-95 253E-01 8.llE-02 5.49£-02 O.OOEOO 1.27E-01 O.OOEOO 257EQ2
'h:JJ7 l.40B02 281E-03 1.29E-03 O.OOEOO 4.268-03 OJXEOO 8.73E02 Nb-95 4.47EOO 249EOO 1.34EOO O.OOEOO 246EOO O.OOEOO 151E04 Nb-97 3.75B02 9.49E-03 3.468-03 O.CXEOO l.llE-02 O.OOEOO 3.50E01 Mo-9'J O.OOEOO l.05EQ2 200E01 O.OOEOO 238E02 0.00EOO 243E02 To-9<Jm 8.97E-03 254B-02 3.23E-01 O.OOEOO 3.85B-01 1.24E-02 1.50E01 To-101, 9.23E-03 133E-02 130E-01 O.OOEOO 2.39E-01 6.?JE-03 4.00E-14 Ru-103 451EOO O.OOEOO l.94EOO O.<XEOO l.72E01 O.OOEOO 5.26EQ2 Ru-105 3.75E-01 O.OOEOO 1.48E-Ol 01XJEOO 4.85EOO O.OOEOO 2.29EQ2 Ru-106 6.70E01 O.OOEOO 8.48EOO O.CXEOO 1.29E02 O.OOEOO 4.34E03 Rh-103m 451EOO O.OOEOO l.94EOO O.OOEOO l.72E01 O.OOEOO 5.26E02 Rh-105 295EOO 216800 l.42EOO O.OOEOO 9.16EOO O.CXJEOO 3.43E02 Rh-106 6.70E01 O.OOEOO 8.48EOO O.OOEOO l.29E02 O.OOEOO 4.34E03 Ag-llOm 9.48E-Ol 8.77E-Ol 521E-01 O.OOEOO l.72EOO O.OOEOO 358E02 Sn-113 5.60E04 157E03 312E03 927E02 0.(XJEOO O.OOEOO 157E05 Sn-117m 3.84E03 3.73EQ2 9.48E02 274E02 O.OOEOO O.OOEOO l.62E05 Sb-122 655E-Ol 128E-02 1.90E-01 9.0ffi..03 O.CXlEOO 3.4(E..()1 l.86E02 Sb-124 7.87EOO l.49J3.01 3.12EOO l91E-02 O.OOEOO 6.13EOO 2.23E02 Sb-125 5.03EOO 5.62E-02 l.20EOO 5.llB-03 O.OOEOO 3.88EOO 5.54E01 Sb-126 3.23EOO 6.58E-02 l.17EOO 1.98E-02 O.OOEOO 1.98EOO 264E02 Sb-127 725E-01 159E-02 278E--01 8.71B-03 O.OOEOO 4JOO..Ol 1.f,6EQ2 Te-125m 257E03 9.30E02 3.44E02 7.71E02 l.04E04 O.OOEOO l.03E04 Te-127m 6.49E03 232E03 7.90002 1$03 263E04 O.OOEOO 217E04 Te-127 l.05E02 3.78E01 228E01 7.81E01 4.29E02 O.OOEOO 832E03 Te-129m 1.10004 4.11E03 l.74E03 3.78E03 4.(,()£04 O.OOEOO 555E04 Te-129 3.0lEOl 1.13E01 733EOO 231E01 126E02 O.OOEOO 227E01 Te-131m lfi6E03 8.10E02 6.75E02 128E03 821E03 O.OOEOO 8.05E04 Te-131 1.89E01 7.88EOO 5.96EOO 155E01 827E01 O.OOEOO 267EOO Te-132 241E03 156E03 l.47E03 l.72E03 1.5CE04 O.OOEOO 739E04 Te-134 3.10001 203E01 125E01 271E01 1.96EQ2 O.OOEOO 3.448-02 I-129 1.19E02 l.02E02 335EQ2 263E05 219E02 O.OOEOO l.61E01 1-130 275E01 8.lOEOl 3.20E01 6.87E03 l.26E02 O.OOEOO 6.97E01
Beave r Valley Power Station Procedure Number:
1/2-0DC-2.01 Trtle:
Unit Level OfUse:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Revision: Page Number.
1~ 39 nf 4~
ATTACH MENT B Page 3 of3 INGEST ION DOSE COMMIT MENT FACTOR S Att VALVES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/br per uCi/mL)
NUCIIDE BONE INER T-BODY IlIYROID KIDNEY WNG GI--TII I-131 1.51E02 216E02 1.24E02 7.08E04 3.71E02 0.<XEOO 5.70E01 I-132 737EOO 1.97E01 6.9(E(X) 6.90E02 3.14E01 0.OOEOO 3.71EOO I-133 5.16E01 8.97E01 274E01 131.E04 l.57E02 0.OOEOO 8.06801 I-134 3.85EOO 1.05E01 3.74EOO 1.81E02 1.(,6801 0.CXEOO 9.12.E-03 I-135 1.61E01 421E01 1.55E01 278E03 6.76E01 0.OOEOO 4.76E01 Cs-134 298E05 7J1JE05 s.mos 0.OOEOO 2.29E05 7.61E04 1.24E04 Cs-136 3.11.E04 1.23E05 8.86£04 0.OCEOO 6.85E04 939£03 l.40E04 Cs-137 3.82E05 5.22E05 3.42E05 0.<XEOO 1.77E05 5.89£04 l.01E04 Cs-138 264E02 5.22E02 259£02 0.OOEOO 3.84E02 3.'](JEOl 2.23E-03 Ba-139 9.69£-01 6.90E-04 284E-02 0.OOEOO 6.45E-04 3.92E.Q.4 l.72EOO Ba-140 203E02 255B-01 133E01 o.cmoo 8.(i6B..Q2 1.46E-01 4.18E02 Ba-141 4.7IB01 3.56E-04 159E-02 0.CXEOO 33IB04 202E-04 222.E-10 B&-142 213E-01 219E-04 1J4E.02 0.OOEOO 1.85E-04 1.24E04 3.00E-19 La-140 l.51B01 7.59E-02 201.B-02 0.OOEOO 0.OOEOO 0.OOEOO 5.57E03 La-142 7.71B-03 3.51E-03 8.74E-04 0.OOEOO 0.OOEOO 0.OOEOO 256£01 Ce-141 263E-02 1.788-02 201.E-03 0.CXEOO 8.26B-03 0.OOEOO 6.80E01 Ce-143 4.64E-03 3.43EOO 3.79E-04 0.<XEOO 1.51E-03 0JXlEOO 128E02 Ce-144 137EOO 5.73E-Ol 7.36B-02 0.OOEOO 3.40E-01 0.OOEOO 4.64E02 Pr-143 5.54E-01 2.22E-01 275E-02 0.OOEOO 1.28E-01 0.OOEOO 243E03 Pr-144 l.8IB-03 7.53E-04 912.E-05 0.OOEOO 4.25E-04 0.OOEOO 26IB-10 Nd-147 3.79E-Ol 438E-01 262E-02 0.<XEOO 2.56E-01 0.OOEOO 210£03 Pm-147 4.54ID) 427E-01 1.73E-01 0.OOEOO 8.08E-01 0.CXEOO 538E02 Pm-149 9.16B-02 1300-02 5.29E-03 01XJEOO 245E-02 0.OOEOO 243E03 Sm-151 4.16EOO 7.17E-01 l.72E-Ol 0.OOEOO 8.02E-01 0.OOEOO 3.17E02 Sm-153 5.16B-02 431.E-02 3.lSE-03 0.<XEOO 139E-02 0.CXJEOO 1.54E03 W-187 296E02 247E02 8.65E01 0.OOEOO 0.OOEOO 0.OOEOO 8.10E04 Np-239 2900-02 2.85E03 1.57E-03 0.OOEOO 8.89E-03 0.OOEOO 5.85E02
Proccdurc Number:
Beaver Valley Power Station l/2-0DC- 2.01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Page Number:
Ml nf 41.
ATTACH MENT C Page 1 of3 LIQUID RADWASTE SYSTEM FIGURE 1.4-1 BV-1 LIQUID RADWASTE SYSTEM STREAM UNIT 1: COLLEC TION, TREATM ENT, & DISCHA RGE Reactor Coolant Cesium Coolant Recovery Tanks From Unit2 Letdown or Removal Ion H Exchangers 2BRS-IOE21A/21B:
Reactor Plant 1BR-TK.-4A/4B lBR-1-lA/lB I 95,000 gal/tank See Attachment C non-aerated page2 of3 drains Containment Sump Waatc Drains Tanks Liquid Waste Ion Exchanger Pre-filter Resin Veueh, RWRO Liquid Waste Efllumt Radiation BVPS-2 1LW-1K-2A/2B ILW-FL-7, ILW-1-3-1, Cooling Aux Bldg Sumps ILW-1-3-2, lLW-1-3-3 Monitor 5,000 gal/tank Tower
'-i ILW-1-34, ILW-FL-8,' f- Blowdown Laboratory Drains ILW-RWR0-1, ILW-1-3-5;- RM-lLW-104 1LW-1K-3A/3B 7,800 gpm ILW-1-3-6 r+ 2,000 gal/tank Reactor Plant Samples BVPS-1 Cooling Miscellaneous Sources Steam Generator 1L__l* Tower Blowdown Tanks
- Blowdown 1LW-1K-7At7B 15,000 gpm 34,500 gal/tank - I Steam Gen. Pre-filter i---..ir ~
Backwash Unit 1 Chemical Waste H From Untt2 To Unit 2 Sump 2LWS-TK21A/21B 01 GOTO 16,000 gal 2SGC-TK23A/23B: ~ Attachment C See Attachment C page2 of3 page 2 of3 Laundry and Laundcy Contaminated Drains Tanks Drains Efflue.nt BVPS1&2 Contaminated Shower Drains 1---- --~~ Radiation M~~ Combined 1LW-1K-6A/6B Cooling Tower 1200 gal/tank RM-lLW-116 Discharge Point 22,800 gpm
Beave r Valley Power Station Procodurc Number:
1/2-0DC-2.01
Title:
Unit: Leve!OfUse:
l/2 General Skill Reference ODCM: LIQUID EFFLUE NTS Rcviaion: Pago Ntnllffl':
18 41 nf4~
ATTACH MENT C Page 2 of3 LIQUID RADWASTE SYSTEM FIGURE 1.4-2 BV-2 LIQUID RADWA STE SYSTEM 1
STREAM UNIT 2: COLLECTION, TREATMENT, & DISCHARGE Reactor Coolant Cesium Removal Ion Letdown Exchangers
-+
2BRS-IOE21A/21B To Unit1 GOTO Attachment C Page I of3 r Liquid Waste Ion Steam Generator n Containment Sump Liquid Waste Exchanger Blowdown BVPS-1 Drains Tanks Resin Vessels, Test Tanks
-+ Cooling Aux Bldg Sumps Clean-up Filters r+
2LWS-TK2 IA/2IB r+ and Strainers 2SGC-TK23A/23B Tower Blowdown Miscellaneous Sources 10,000 gal/tan1c +- 18,000 gal/tank 15,000 gpm 2SOC-IOE21A/21B Reactor Plant Samples Laboratory Drains Steam Generator Condensate ~
BVPS-2 Cooling Tower Hold Tanks ,i, Blowdown Condensate 7,800 gpm Demineralizer Liquid Waite Rinse Water 2SGC-TK21A/21B 50,000 gal/tank
~
~
Effluent Radiation ~ I Monitor ,...
From Unftl ! 2SGC-RQIOO 1LW-TK-7A/7B:
See Attachment C - H Sump page 1 of3 u BVPSI&2 Combined Cooling Tower Cable Vault Sump Discharge Point Unit 2 Catch Basin System 22,800 gpm 2,424gal I I
Procedure Number.
Beaver Valley Power Station l/2-0DC-2.01 Trtle:
Level Of Use:
General Skill Reference ODCM: LIQUID EFFLUENTS Revia.ion: Page Number:
ATTACHMENT C Page 3 of3 LIQUID RADWASTE SYSTEM FIGURE 1.4-3 BV-1 AND 2 LIQUID EFFLUENT RELEASE POINTS 012 ERFBlda HVAC Dilcharge YardStonn BV-20il .t. Yard Runoff& Water Storm Fire SepmatorNo Runoff&
Protection 22&BV-2 Pirc
. Diesel Pro1ffllon BV*l Primay&
Scoondny Heat Oeocntor &
pn&Chillcn Turbine Bldg Dn1m Malnlmakc Yard Storm Ruooft' .t.
Debris Fire Protcctioo, Removal and BV-t Pump House Roof Bac:kwub Yard Storm Runoff°&. Pirc BV-2 Scrvk:c Wala' Protocdoo Strainer Backwash BV-1&2 BV-t EmcrseocY Coolins Tower BV-lOU BV-200 Overftow,and Watc:1' Wllla Condculllte BV-t Clrculatin& Water System Separator No Sepa.ator Slowdown&. Drain During <>utaae 23 &BV-2 Noll lJncoatmnmatccl TmbincBldg RJvor Water Floor&
Equipment BV-2 Primary & Drams BV-1 Settlin& Basin, Secooduy Heat BV-1 Clarifl~. ~&.
BV-1 Filters Cblllen BV-20D Water Separator No 24 &.
BV-2 BV-2 Yard Coolin& Storm Tower Runoff&
Pirc Slowdown Protecdoo BV-1 Cooling BV-2 Tower UquJd Radloacdve Blowdown Walle Effluent BV-1 Mile Wme8mnpl, BV-2Coatrol BV-1 Cl,emical Bldg & Cable Tunnel Tramtorm<< Sia& Pits.
BV-t Llquid Waste Sump and BV-2 Servioe Water Valve Pits, BV-2 Radioeotivc Cod Lab Sink CoocJc:,ngp, PoUsb &. CINYnbcll Safeguard Wasie Effluent Drains Valve Pit, Demlnerallzed Water Sumps
Beav er Valle y Power Station Procedure Number:
1/2-0DC-2.01
Title:
Unit I Level OfUsc:
General Skill Referenc e ODCM: LIQUID EFFLUENTS Revision: I Page Number.
ATTAC HMEN T D Page 1 of 1 SITE BOUN DARY FOR LIQUID EFFLU ENTS FIGUR E 5-1 SITE BOUN DARY FOR LIQUID EFFLU ENTS
,' ...,I ~,~
~-1 j
I I
_,, I ""'I ~
I I
I f Ij I
- 15
- ~
Z5 I
-8.
C) m ...,,,.... C
- a
........ C.
- c
- . *t
~
--.:i ~
~~
I en g]
...fr ...;
I
, f~ :u ... QI "Cl II , Ii.'" "'~
0<D111 .... QI I .,_ >.cl oo'"'m
- .... QI
, l:'"1:1 111 I I .a!::~t I , i::i::i.11 :~
- I 111 Ill 1:2 I , 0 :I IZl;::lJ k,8
- I I *
- .~~'"':11
,. m..., .u1 Cl)"l:l"l:li:>: : ....
- ~4- .,* .....,"S.:!o C" u ....
I) 4-it i9::1!lc§fl