ML071230120
| ML071230120 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/2006 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-07-060 RTL A9.621B | |
| Download: ML071230120 (384) | |
Text
{{#Wiki_filter:Enclosure 2, Attachment 2 Beaver Valley Power Station -Units 1 & 2 Annual Radioactive Effluent Release Report Calendar Year -2006 Attachment 2 Unit I and 2 Offsite Dose Calculation Manual Changes...... ...... ......... ................... ................... ..................................................... .............................. ..................................................... ................. ..................
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...............................X. -::- -::- -: ............. ............... ................................................. In o n :::... ... ................................ ....... ............ ....... ............................. .. .... ............................................... Attached is a complete copy of the ODCM that includes: Change (22) of the ODCM (Effective: August, 2006)Change (23) of the ODCM (Effective: December, 2006)................ ............. ........................ ............. .. Z 0144"fil: 6466. .................... .......... ................t ..............................A complete copy of the ODCM has been provided to the following offices: United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 United States Nuclear Regulatory Commission Regional Administrator 475 Allendale Road King of Prussia, PA 19406 For a complete copy of the ODCM, contact Mr. Anthony T Lonnett at 724-682-7523. RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-1.01 ODCM: Index, Matrix and History of ODCM Changes Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 5 Level Of Use General Skill Reference Safety Related Procedure
- Yes Beaver Valley Power Station Procedure Number: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number: W-5 2 of 7 TABLE OF CONTENTS 1.0 P U R P O SE ........................................................................................................................................ 4 2.0 SCOPE ..................................................................................... 4
3.0 REFERENCES
AND COMMITMENTS ....................................... 4 3.1 References Used in This Procedure .................................................................................. 4 3.2 Summary of References Used Throughout Other Procedures of the ODCM ................... 5 3.3 C om m itm ents ....................................................................................................................... 12 4.0 RECORD S A N D FORM S ............ ............................................................................................ 12 4 .1 R e sord s ................................................................................................................................. 13 4 .2 F o rm s .................................................................................................................................... 13 5.0 PRECAUTIONS AND LIMITATIONS ..................................................................................... 13 6.0 A CCEPTAN CE CRITERIA ........................................................................................................ 14 7.0 PR E R E Q U ISIT E S .......................................................................................................................... 14 8.0 PR O C E D U R E ................................................................................................................................ 14 8.1 Description of ODCM Structure ....................................................................................... 14 8.1.1 1/2-ODC-1.01, ODCM: Index, Matrix and History of ODCM changes ...... 14 8.1.2 1/2-ODC-2.01, ODCM: Liquid Effluents ...................................................... 15 8.1.3 1/2-ODC-2.02, ODCM: Gaseous Effluents ................................................... 16 8.1.4 1/2-ODC-2.03, ODCM: Radiological Environmental Monitoring Program ...... 16'8.1.5 1/2-ODC-2.04, ODCM: Information Related to 40 CFR 190 ........................ 17 8.1.6 1/2-ODC-3.01, ODCM: Dispersion Calculational Procedure and Source Term Inp uts .................................................................................................................. 17 8.1.7 1/2-ODC-3.02, ODCM: Bases for ODCM Controls ...................................... 17 8.1.8 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs ............... 18 8.2 H istory O f O D CM Changes ............................................................................................... 19 8.2.1 Change (1) of BV-I ODCM (Issue 1), Effective January, 1984 ..................... 19 8.2.2 Change (2) of BV-I ODCM (Issue 1, Rev 1), Effective October, 1984 ...... 19 8.2.3 Change (3) of BV- 1 ODCM (Issue 1, Rev 2), Effective July, 1986 ................ 19 8.2.4 Change (4) of BV-1 ODCM (Issue 2), and BV-2 ODCM (Issue 1, Rev 1), Effective July, 1987 ........................................................ 20 8.2.5 Change (5) of BV-1 ODCM (Issue 2, Rev 1), and BV-2 ODCM (Issue 1, Revision 2), Effective December, 1987 .......................................................... 21 8.2.6 Change (6) of BV-1 ODCM (Issue 2, Rev 2), and BV-2 ODCM (Issue 1, Rev 3), Effective June, 1989 ....................................................................................... 21 8.2.7 Change (7) of BV-1 and 2 ODCM (Issue 3), Effective August, 1995 ............ 23 8.2.8 Change (8) of BV-1 and 2 ODCM (Issue 3, Rev 1), Effective October, 1995 .... 28 8.2.9 Change (9) of BV-1 and 2 ODCM (Issue 3, Rev 2), Effective May 1997 ..... 31 8.2.10 Change (10) of BV-l and 2 ODCM (Issue 3, Rev 3), Effective June 1997 ........ 32 8.2.11 Change (11) of BV-1 and 2 ODCM (Issue 3, Rev 4), Effective March 1998 ..... 32 8.2.12 Change (12) of BV-1 and 2 ODCM (Issue 3, Rev 5), Effective November 199834..,. 8.2.13 Change (13) of BV-1 and 2 ODCM (Issue 3, Rev 6), Effective May 1999 ........ 31'." 8.2.14 Change (14) of BV-1 and 2 ODCM (Rev 14), Effective March 2000 ........... 36 8.2.15 Change (15) of BV-1 and 2 ODCM (Rev 15), Effective August 2000 ........... 37 .8.2.16 Change (16) of BV-1 and 2 ODCM (Effective April 2002) ............................ 38 Beaver Valley Power Station Procedureul/2,r:ODC-l.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 3 of 78 8.2.17 8.2.18 8.2.19 8.2.20 8.2.21 8.2.22 ATTACHMENT A ATTACHMENT B ATTACHMENT C TABLE OF CONTENTS Change (17) of BV-I and 2 OCDM (Effective August 2002) ........................ 41 Change (18) of the BV-I and 2 ODCM (Effective October 2002) ................ 42 Change (19) of BV-I and 2 ODCM (Effective November 2002) .................. 43 Change (20) of BV-I and 2 ODCM (Effective October 2003) ....................... 43 Change (21) of BV- 1 and 2 ODCM (Effective November 2004) .................. 46 Change (22) of BV-I and 2 ODCM (Effective March 2005) .......................... 49 LIST OF ODCM TABLES ............................................................................. 53 LIST OF ODCM FIGURES ........................................................................... 59 ODCM CONTROLS PROCEDURE MATRIX ............................................. 60 Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: " 1 5 4. .4of78 1.0 PURPOSE 1.1 This procedure provides an index for the entire Offsite Dose Calculation Manual (ODCM).1.2 This procedure also provides an historical description of all changes to the ODCM.1.3 This procedure also contains a matrix of plant procedure references for Radiological Effluent Technical Specifications (RETS), Radiological Environmental Monitoring Program (REMP)surveillances that were transferred from the Technical Specification Procedure Matrix to the ODCM via Change (8) and Change (16).1.3.1 Prior to issuance of this procedure, these items were located in the Index and Appendix F of the old ODCM.1.3.2 The numbering of each specific ODCM Controls, ODCM Surveillance Requirements and ODCM Controls Tables contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Controls, ODCM Surveillance Requirements and ODCM Controls Tables numbers remained the same when they were transferred from the Technical Specifications Procedure Matrix. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes. V 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
Used in This Procedure 3.1.1 NUREG-0472, Draft 7 for Rev. 3, Standard Radiological Effluent Technical Specifications For PWRs September, 1982.3.1.2 NUREG-0133, Preparation Of Radiological Effluent Technical Specifications For Nuclear Power Plants, October, 1978.3.1.3 Generic Letter 89-01, Implementation Of Programmatic Controls For Radiological Effluent Technical Specifications In The Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The ODCM Or To The PCP, January 31, 1989.3.1.4 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls For Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April, 1991.3.1.5 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs Beaver Valley Power Station Procedure Number: 1/I2-ODC-I .01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 5 of 78 3.1.6 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.7 1/2-ADM-0100, Procedure Writer's Guide 3.1.8 NOP-SS-3001, Procedure Review and Approval 3.1.9 CR04-09895, Missed ODCM Channel Functional Test (Gas Effluent Sampler Flowrate). CA-04, Revise ODCM procedure 1/2-ODC- 1.01, Attachment C, Table F:3a to show that the Channel Functional Test requirements for the Unit I Sampler Flowrate Measuring Devices delineated in ODCM procedure 1/2-ODC-3.03, Attachment F, Table 4.3-13 are being met by Form 1/2-ENV-01.04.F01 instead of 1MSP-43.71-I 3.1.10 CR05-01169 Chemistry Action Plan For Transition of RETS, REMP and ODCM, CA-14 thru CA-2 1, Revise ODCM procedures to change document owner from "Manager, Radiation Protection" to Manager Nuclear Environmental & Chemistry". 3.1.11 CR06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure 1/2-.ODC-2.01 to update the alarm setpoints of [RM- 1 RM- 100] and [RM-IDA- 100] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275. Also, CA-04; revised ODCM procedure 1/2-ODC-2.02 to add a"<" designation to all alarm setpoints for Unit 1 and Unit 2 low range noble gas effluent monitors.3.1.12 CR06-6476, 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-RQ101] for incorporation of the Extended Power Uprate per Unit 2 TS Amendment No. 156.3.2 Summary of References Used Throughout Other Procedures of the ODCM 3.2.1 BVPS- 1 and 2 UFSAR: 3.2.1.1 BVPS-1 UFSAR Section 11.2.3; Gaseous Waste Disposal System 3.2.1.2 BVPS-l1UFSAR Section 11.2.4; Liquid Waste Disposal System 3.2.1.3 BVPS-2 UFSAR Section 11.2; Liquid Waste Management Systems 3.2.1.4 BVPS-2 UFSAR Section 11.3; Gaseous Waste Management Systems 3.2.2 Condition Reports: 3.2.2.1 CR 971578, MEMBERS OF THE PUBLIC Discrepancies. CA-01, Revise Section 4 of the ODCM to clarify how doses due to effluents for members of the public (conducting activities inside the site boundary) are derived and reported.3.2.2.2 CR 980129, ODCM Procedure Matrix Discrepancies. CA-01, Revise Appendix F of the ODCM to correct discrepancies with 1/2-OM L5 Surveillance Logs. Pro~cedure Number Beaver Valley Power Station___________________________________________I12:ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill'Reference ..ODCM: Index, Matrix and History of ODCM Changes Revision: Page N0mber: 3.2.2.3 CR 980353, EPMP 2.01 Discrepancies for Environmental Sampling Locations. CA-01, Revise Section 3 of the ODCM to correct REMP sample site distances and sectors.3.2.2.4 CR 981488, Chemistry Related ODCM Procedures and ODCM Appendix F References. CA-01, Revise ODCM Appendix F to add Chemistry procedure references. 3.2.2.5 CR 981489, ODCM Table 4.11-2 Row A (Waste Gas Storage Tank Discharge Tritium). CA-01, Revise Appendix C of the ODCM (Table 4.11-2) to add clarification as to where and when tritium samples are to be obtained for GWST discharges. 3.2.2.6 CR 981490, ODCM Table 4.11-2 Note e, and Related Chemistry Department Procedures. CA-01, Revise Appendix C of the ODCM (Table 4.11-2, Note e) to specify the proper tritium sample point.3.2.2.7 CR 982097, Liquid Discharge Post Release Review Methodology. CA-01, Revise Section 1 of the ODCM to add clarification for calculation of radionuclide concentration when the Post Dose Correction Factor is > 1.3.2.2.8 CR 990025, Unnecessary Radiation Monitor Setpoint Change After Waste Discharges. No ODCM changes are required for this CR.3.2.2.9 CR 992652, Discrepancies Concerning ODCM Surviellances of Unit I Gaseous Effluent Instrumentation. CA-02, Revise Appendix F of the ODCM to make proper reference to the HP Shift logs.3.2.2.10 CR 993021, Apparent Failure to Test RM-DA-100 Trip Function as Required by ODCM. No ODCM changes are required for this CR.3.2.2.11 CR 001682, ODCM Action 28 Guidance. CA-02, Revise Appendix C of the ODCM (Table 3.3-13, Action 28) to differentiate actions associated with Inoperable Process Flow Rate Monitors vs. Sample Flow Rate Monitors.3.2.2.12. CR02-05533,.Procedure 1/2-ODC-3.03, ATTACHMENT E Missing Information. CA-01, Revise ODCM procedure 1/2-ODC-3.03 (Table 3.3-12) to include minimum channels operable and associated actions when Flow Rate Measurement Device [FR-1LW-103] is inoperable. 3.2.2.13 CR02-0571 1, TS and ODCM changes not reflected in 1OM-54.3.L5 Surveillance Log. CA-01, Revise 1/2-ODC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes. ___.j Procedure Number: Beaver Valley Power Station P1/2dODC-m.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 7 of 78 3.2.2.14 CR02-06174, Tracking of Activities for Unit 1 RCS Zinc Addition Implementation. CA-13, Revise ODCM procedure 1/2-ODC- 1.01 to include a discussion as to why Zn-65 is being added to the ODCM. CA-14, Revise ODCM procedure 1/2-ODC-2.01 (Tables 1.1-l a and I b) to include the addition of Zn-65 to ODCM liquid source term.3.2.2.15 CR 03-02466, RFA-Radiation Protection Effluent Control Provide Recommendation on Processing when Performing Weekly Sample of [1 LW-TK-7A/7B]. CA-02, Revise ODCM Procedure 1/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit I and Unit 2.3.2.2.16 CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit I Containment Vacuum Pump Source-Term in ODCM procedure 1/2-ODC-2.02, Attachment A, Table 2.1-l a.3.2.2.17 CR03-06123, Enhance Table 3.3-6 of 1/2-ODC-3.03 to Add More Preplanned Method of:Monitoring. CA-01, Revise Table 3.3-6 and Table 4.3-3 to allow use of Eberline SPING Channel 5 as an additional 2 nd PMM when the Unit I Mid or High Range Noble Gas Effluent Monitors are Inoperable. 3.2.2.18 CR03-06281, Gaseous Tritium Sampling Required by ODCM (1/2-ODC-3.03) Unclear for Chemistry. CA-01, Revise procedure Attachment K Table 4.11-2 for RP & Chemistry sampling of Gaseous Effluent Pathways to show which effluent pathways need sampled for compliance to ODCM Control 3.11.2.1 requirements. 3.2.2.19 CR03-07487, Results of NQA Assessment of the Radiological Effluents Program.CA-01, Revise Calculation Package No. ERS-ATL-95-007 to clarify the term"Surface Water Supply" per guidance presented in NUREG-0800 SRP 15.7.3. CA-05, Revise 1/2-ODC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.3.2.2.20 CR03-07668, Benchmark Effluent & Environmental Programs VS Papers Presented at 13th REMP/RETS Workshop. CA-01, Evaluate procedure Attachment K Table 4.11-2 to reduce the amount of Effluent Samples obtained during a power transient. 3.2.2.21 CR03-09288, LAR IA-321 & 2A-193, Increased Flexibility in Mode Restraints. CA- 19, Review LAR 1A-321/2A-193 to identify the affected Rad Effluent procedures, programs, manuals, and applicable plant modification documents that will need to be revised to support implementing the LAR.3.2.2.22 CR03-09959, RFA-Rad Protection Provide Clarification to ODCM 1/Day Air Tritium Sample. CA-01, Revise ODCM procedure 1/2-ODC-3.03 Attachment K (Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere. Procedure Number: Beaver Valley Power Station 1/2!ODC-1.01 Title: Unit: Level Of Use: il1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 3.2.2.23 CR03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure I/2-ODC-3.03, Attachment 0, Control 3.11.2.5 to correct a typographical error. Specifically, the final word in Action (a) needs changed from"nad" to "and".3.2.2.24 CR04-00149, Radiation Protection Performance Review Committee Action Items.CA- 12. Incorporate the Global Positioning System [GPS] in the Radiological Environmental Monitoring Program.3.2.2.25 CR04-01643, Procedure Correction -Typographical Error in the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment F, (Table 3.3-13 and 4.3-13)to correct a typographical error. Specifically, the Asset Number for the Vacuum Gauge used for measurement of sample flow (from the Alternate Sampling Device) needs changed from [PI-IGW-13] to [PI-1GW-135]. 3.2.2.26 CR04-02275, Discrepancies in Table 3.3-13 of the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to add clarification that the "Sampler Flow Rate Monitors are the devices used for"Particulate and Iodine Sampling". 3.2.2.27 CR05-01169, Chemistry Action Plan For Transition of RETS, REMP and ODCM, ..CA-14 thru CA-21, Revise ODCM procedures to change document owner from"Manager, Radiation Protection" to Manager Nuclear Environmental &Chemistry". 3.2.2.28 CR05-01390, Include GPS data in.2004 REMP Report and related 1/2-ODC and 1/2-ENV procedures. CA-02, revise ODCM procedure 1/2-ODC-2.03 to include an update of REMP sample locations (using the GPS Satellite data).3.2.2.29 CR 05-03306, Incorporated Improved Technical Specifications (ITS).3.2.2.30 CRO5-03854, ODCM Figure for Liquid Effluent Release Points Needs 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. 3.2.2.31 CR06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure 1/2-ODC-2.01 to update the alarm setpoints of [RM- IRM- 100]and [RM- IDA- 100] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275. Also, CA-04; revised ODCM procedure 1/2-ODC-2.02 to add a"<" designation to all alarm setpoints for Unit 1 and Unit 2 low range noble gas effluent monitors.3.2.2.32 CR06-6476, 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-RQ 101 ] for incorporation of the Extended Power Uprate per Unit 2 TS Amendment No. 156. Beaver Valley Power Station Procue Numbr: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 9 of 79 3.2.3 Calculation Packages: 3.2.3.1 ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for HPM-RP 6.5, Issue 3 and Later 3.2.3.2: ERS-SFL-85-03 1; Gaseous Effluent Monitor Efficiency Data 3.2.3.3 ERS-ATL-86-008; ODCM Alarm Setpoint Revisions for Gaseous Monitors 3.2.3.4 ERS-HHM-87-014; Unit 1/2 ODCM Gaseous Effluent Monitor Alarm Setpoint-Determinations 3.2.3.5 ERS-ATL-87-026; BVPS-1 and BVPS-2 ODCM T Factor Justification 3.2.3.6 ERS-ATL-89-014; Verification/Validation of ODCM R Values 3.2.3.7 ERS-ATL-90-021; Justification for Removal of Technical Specification Process Flowrate Measurement Requirements for 2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ 112 3.2.3.8 ERS-ATL-95-006; Re-evaluation of TS/ODCM SR's 4.11.1.1.3, 4.11.1.1.4 and Notes e and g of TS/ODCM Table 4.11-1 3.2.3.9 ERS-ATL-95-007; Verification of Outside Storage Tank Activity Limit of TS 3.11.1.4 3.2.3.10 Stone and Webster UR(B)-160; BVPS Liquid Radwaste Releases and Concentrations -Expected and Design Cases (Per Unit and Site)3.2.3.11 Vendor Calculation Package No. 8700-UR(B)-223, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternate Source Terms on the Alarm Setpoints for the. Radiation Monitors at Unit 1 3.2.3.12 Engineering Change Package No. ECP-04-0440, Extended Power Uprate (Unit 1)3.2.3.13 Vendor Calculation Package No. 8700-UR(B)-508, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternate Source Terms on the Alarm Setpoints for the Radiation Monitors at Unit 2 3.2.3.14 Engineering Change Package No. ECP-04-0440, Extended Power Uprate (Unit 2)3.2.4 Internal Letters: 3.2.4.1 DLC Response to NRC Unresolved Item 50-334/83-30-05, Radiation Monitor Study- Particle Distribution Evaluation, November 26, 1986.3.2.4.2 ND1SHP:776; BVPS-1 ODCM Table 2.2-2, Appendix B, February 12, 1988 Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference.,, ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 4 I 5 10 of 78 S 3.2.4.3 ND3NSM:343 1; Technical Specification Verification Effort, August 11, 1988 3.2.4.4 NDLNSM:3522; Technical Specification Verification Effort Checklist, September 14, 1988 3.2.4.5 ND1NSM:3652; Technical Specification Verification Effort, November 21, 1988 3.2.4.6 NPD3SHP:2466; Self Assessment of the Liquid and Gaseous Effluent Processes at BVPS -Final Report, July 16, 1997 3.2.4.7 -NPD3SHP:2257; ODCM Liquid Waste Recirculation Rates, February 11, 1998 3.2.4.8 NPD3SHP:2643; Action 28 of ODCM Appendix C Table 3.3-13, January 14, 1999 3.2.4.9 ND3MNO:4309; Response to Request for Technical Specification Interpretation, April 20, 1999.3.2.5 Contractor Technical Evaluation Reports: 3.2.5.1 EGG-PHY-8194; Technical Evaluation Report for the Evaluation of ODCM Updated through Issue 2, Revision 1, Beaver Valley Power Station, Unit 1, September 1988 3.2.5.2 EGG-PHY-8217; Technical Evaluation Report for the Evaluation of ODCM updated through Issue 1, Revision 2, Beaver Valley Power Station, Unit 2, September 1988 3.2.5.3 NUS-2173; Development of Terrain Adjustment Factors For Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Dispersion Model, June 1978 3.2.5.4 UCRL-50564; Concentration Factors of Chemical Elements in Edible Aquatic Organisms, Revision 1, 1972 3.2.6 NRC Letters: 3.2.6.1 Unit 1 Technical Specification Amendment 66, March 28, 1983 3.2.6.2 Beaver Valley Unit 2 -Offsite Dose Calculation Manual, ODCM (TAC 63996), July 14, 1987 3.2.6.3 Beaver Valley Units I and 2 -Acceptance of the Offsite Dose Calculation Manuals (TAC 93996 and 67421), March 2, 1989 3.2.6.4 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-188/2A-70 (LAR I A-175/2A-3 7), Implemented August 7, 1995 Beaver Valley Power Station ProcedureNumber: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 11 of 78 3.2.6.5 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-194/2A-77 (LAR's 1 A-231/2A-101), Implemented December 1, 1995 3.2.6.6 Unit 1/2 Technical Specification Figure 5.1-2, including Amendments 1A-202/2A-83 (LAR 1A-234/2A-107, Implemented June 9, 1997 3.2.6.7 Unit 1/2 Technical Specifications 6.9.1'10 and 6.9.2, including Amendments 1 A-220/2A-97 (LAR 1 A-246/2A-116), Implemented May 20, 1999 3.2.6.8 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 1A-246/2A-124 I -(LAR 1A-287/2A-159), Implemented April 11, 2002 3.2.6.9 Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5, 6.8.6, and 6.9.2 including Amendments IA-250/2A-130 (LAR 1 A-291/2A-163), Implemented August 7, 2002 3.2.7 NUREG's: 3.2.7.1 NUREG-0017, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors, (PWR- Gale Code), Revision I, April 1985 3.2.7.2 NUREG 0133; Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants, October 1978 3.2.7.3 NUREG-0 172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, November 1977 3.2.7.4 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations, September 1977 3.2.7.5 NUREG-0472; Radiological Effluent Technical Specifications for PWR's.3.2.7.6 NUREG-0800, Standard Review Plan, Postulated Radioactive Releases Due to Liquid-Containing Tank Failures, July 19811 3.2.7.7 NUREG-1301; Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.. 1), April 1991 3.2.7.8 NUREG-1431; Standard Technical Specification -Westinghouse Plants Specifications 3.2.7.9 NUREG/CR-2919; Meteorological Evaluation of Routine Effluent Releases At Nuclear Power Stations, September 1982 3.2.8 Regulatory Guides: Procedure Number: Beaver Valley Power Station, 1/2.ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference.: ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:-5 12o07 S 3.2.8.1 RG-1.23; Meteorological Measurement Program For Nuclear Power Plants 3.2.8.2 RG-1. 109; Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, April 1977 3.2.8.3 RG-1.111; Methods For Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977 3.2.8.4 RG-1.1 13; Estimating Aquatic Dispersion of Effluents From Accidental and Routine Reactor Releases For The Purpose of Implementing Appendix I, April 1977 3.3 Commitments 3.3.1 10 CFR Part 20, Standards for Protection Against Radiation 3.3.2 10CFR20.1302, Compliance with Dose Limits for Individual Members of the Public.3.3.3 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities 3.3.4 10CFR50:36a, Technical Specifications on Effluents from Nuclear Power Reactors 3.3.5 Appendix I to 10 CFR Part 50, Numerical Guides For Design Objectives and Limiting Conditions For Operation to Meet The Criterion "As Low As Reasonably Achievable" For Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents 3.3.6 40 CFR Part 141 3.3.7 40 CFR Part 190, Environmental Radiation Protection Standards For Nuclear Power Operations
3.3.8 Licensee
Response to NRC Unresolved-Item 50-334/83-30-05. The Radiation Monitor Particle Distribution Evaluation showed that the Licensee must continue to use correction factors to determine particulate activity in samples obtained from the effluent release pathways.3.3.9 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. Beaver Valley Power Station, Procedure Number: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 13 of 78 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 (eg; letter or calculation package) with an appropriate RTL number.4.1.2 Changes to the ODCM shall be documented and records of reviews shall be retained in accordance with the applicable record retention provisions of the quality assurance pIogram description included in the Updated Final Safety Analysis Report.4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 This OFFSITE DOSE CALCULATION MANUAL (ODCM) provides the information and methodologies to be used by Beaver Valley Power Station Unit I and Unit 2 (BV-1) and (BV-2) to assure compliance with the Administrative Controls Section of the operating Technical Specifications. They are intended to show compliance with 10 CFR 20.1302,(32l) 10 CFR 50.36a,(3"2.2) Appendix I of 10 CFR Part 50(32-3) and 40 CFR Part 190.(3.2.4) 5.2 This ODCM is based on the NUREG's and Generic Letter documents from the United States Nuclear Regulatory Commission.Ca.1 3.12, 3.1.33.3.1.4) Specific plant procedures for implementation of the ODCM are included in various site procedures and documents, and are utilized by the operating staff to assure compliance with Technical Specifications and the CONTROLS Procedure of the ODCM:(3.5)5.3 The ODCM has been prepared as generically as possible in order to minimize the need for future versions. However, some changes to the ODCM may be necessary in the future. Any such changes will be properly prepared, reviewed, and approved as indicated in the Administrative Control Section of the Technical Specifications. Additionally, changes to the ODCM require review and acceptance by the PORC.5.3.1 An implementation procedure for control of the ODCM is included in 1/2-ADM-1 640.(3 1.6)5.4 This procedure also contains information that was previously contained in Appendix F of the previous BV-I and 2 Offsite Dose Calculation Manual.5.4.1 In regards to this, the Tables that were transferred from Appendix F to the appropriate ATTACHMENTS of this procedure will still contain a prefix denoting an "F". Procedure Number: Beaver Valley Power Station o e b2-0DC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 I 14 of 78 Si 5.5 This procedure includes Improved Technical Specifications ([ITS]) information that is NOT applicable to current Technical Specifications ([CTS]) and [CTS] information that is NOT applicable in [ITS]. The [CTS] information shall be used prior to the [ITS] effective date.The [ITS] information shall be used on or after the [ITSJ effective date.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 ýto 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculation.(3'.1.7) , 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100 (3 1'7)and 1/2-ADM-1640. (3.1.6)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001 (3.-8) and 1/2-ADM-1640. (3.1.6)7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.8.0 PROCEDURE 8.1 Description of ODCM Structure 8.1.1 1/2-ODC-1.01, ODCM: Index, Matrix and History of ODCM changes (formerly: ODCM Index and Appendix F)8.1.1.1 History of ODCM Changes 8.1.1.2 Summary of ODCM References 8.1.1.3 List of Tables(ATTACHMENT A)8.1.1.4 List of Figures (ATTACHMENT B)8.1.1.5 Matrix of Procedures Used to Meet ODCM Controls (ATTACHMENT C)8.1.1.5.1 BV- 1 Radiation Monitor Surveillances 8.1.1.5.2 BV-1 Liquid Effluent Monitor Surveillances 8.1.1.5.3 BV-2 Liquid Effluent Monitor Surveillances 8.1.1.5.4 BV- 1 Gaseous Effluent Monitor Surveillances 8.1.1.5.5 BV-2 Gaseous Effluent Monitor Surveillances Beaver Valley Power Station Procedure Number D 1/2-ODC- 1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:-5 15 of 78 8.1.1.5.6 8.1.1.5.7 8.1.1.5.8 8.1.1.5.9 8.1.1.5.10 8.1.1,5.11 8.1.1.5.12 8.1.1.5.13 8.1.1.5.14 8.1.1.5.15 BV-1 and 2 Liquid Effluent Concentration Surveillances BV-1 and 2 Liquid Effluent Dose Surveillances BV-1 and 2 Liquid Effluent Treatment Surveillances BV-1 and 2 Gaseous Effluent Air Dose Surveillances BV-I and 2 Gaseous Effluent Particulate and Iodine Surveillances BV-I and 2 Gaseous Effluent Treatment Surveillances BV-1 and 2 Gaseous Effluent Total Dose Surveillances BV-I and 2 Gaseous Effluent REMP Surveillances BV-I and 2 Gaseous Effluent Land Use Census Surveillances BV- 1 and 2 Gaseous Effluent Interlaboratory Comparison Program Surveillances 8.1.2 1/2-ODC-2.01. ODCM: Liquid Effluents (formerly; ODCM Sections 1 and 5)8.1.2.1 Alarm Setpoints 8.1.2.1.1 BV-I Setpoint Determination Based On A Conservative Mix 8.1.2.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release 8.1.2.1.3 BV-2 Setpoint Determination Based On A Conservative Mix 8.1.2.1.4 BV-2 Setpoint Determination Based On Analysis Prior To Release 8.1.2.2 Compliance With 10 CFR 20 EC Limits 8.1.2.2.1 Batch Releases 8.1.2.2.2 Continuous Releases 8.1.2.3 Compliance With 10 CFR 50 Dose Limits 8.1.2.3.1 Cumulation Of Doses 8.1.2.3.2 Projection Of Doses 8.1.2.4 Liquid Radwaste Treatment System 8.1.2.4.1 BV-I Liquid Radwaste Treatment System Components BPProcedure Number: Beaver Valley Power Station 1!- /2-ODC-1.01 Title: ODCM: Unit: Level Of Use: 1/2 General Skill Reference Revision: Page Number: evsA Pe N nf7R Index, Matrix and History of ODCM Changes 8.1.2.4.2 BV-1 Laundry and Contaminated Shower Drain System Components 8.1.2.4.3 BV-2 Liquid Radwaste Treatment System Components 8.1.2.5 Site Boundary for Liquid Effluents 8.1.2.5.1 Liquid Effluent*Site Boundary 8.1.3 1/2-ODC-2.02, ODCM: Gaseous Effluents (formerly; ODCM Sections 2 and 5)8.1.3.1 Alarm Setpoints 8.1.3.1.1 BV-1 Setpoint Determination Based On A Calculated Mix 8.1.3.1.2 BV- 1 Setpoint Determination Based On Analysis Prior To Release 8.1.3.1.3 BV-2 Setpoint Determination Based On A Calculated Mix 8.1.3.1.4 BV-2 Setpoint Determination Based On Analysis Prior To Release 8.1.3.1.5 BV-1/2 Setpoint Determination Based On A Calculated Mix 8.1.3.1.6 BV-1/2 Setpoint Determination Based On Analysis Prior To Release 8.1.3.2 Compliance With 10 CFR 20 Dose Rate Limits 8.1.3.2.1 Dose Rate Due To Noble Gases 8.1.3.2.2 Dose Rate Due To Radioiodines And Particulates 8.1.3.3 Compliance With 10 CFR 50 Dose Limits 8.1.3.3.1 Doses Due To Noble Gases 8.1.3.3.2 Doses Due To Radioiodines And Particulates 8.1.3.4 Gaseous Radwaste Treatment System 8.1.3.4.1 BV-1 Gaseous Radwaste Treatment System Components 8.1.3.4.2 BV-2 Gaseous Radwaste Treatment System Components 8.1.3.5 Site Boundary for Gaseous Effluents 8.1.4 1/2-ODC-2.03. ODCM: Radiological Environmental Monitoring Program (formerly; ODCM Section 3)8.1.4.1 Program Requirements Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 17 of 78 8.1.5 1/2-ODC-2.04, ODCM: Information Related to 40 CFR 190 (formerly; ODCM Section 4)8.1.5.1 Compliance with 40 CFR 190 Dose Limits 8.1.5.2 Report Requirements 8.1.5.3 Inside the Site Boundary Radiation Doses 8.1.5.3.1 Gaseous Effluent Site Boundary 8.1.6 1/2-ODC-3.01, ODCM: Dispersion Calculational Procedure and Source Term Inputs (formerly; ODCM Appendix A & B)8.1.6.1 Dispersion and Deposition Parameters 8.1.6.2 BV-1 and 2 Release Conditions 8.1.6.3 BV-1 Liquid Source Term Inputs 8.1.6.4 BV-2 Liquid Source Term Inputs 8.1.6.5 BV-1 Gaseous Source Term Inputs 8.1.6.6 BV-2 Gaseous Source Term Inputs 8.1.7 1/2-ODC-3.02, ODCM: Bases for ODCM Controls (formerly; ODCM Appendix D)8.1.7.1 Bases 3.3.3.1: Radiation Monitoring Instrumentation 8.1.7.2 Bases 3.3.3.9: Radioactive Liquid Effluent Monitoring Instrumentation 8.1.7.3 Bases 3.3.3.10: Radioactive Gaseous Monitoring Instrumentation 8.1.7.4 Bases 3.11.1.1: Liquid Effluent Concentration 8.1.7.5 Bases 3.11.1.2: Liquid Effluent Dose 8.1.7.6 Bases 3.11.1.3: Liquid Radwaste Treatment System 8.1.7.7 Bases 3.11.1.4: Liquid Holdup Tanks 8.1.7.8 Bases 3.11.2.1: Gaseous Effluent Dose Rate 8.1.7.9 Bases 3.11.2.2: Dose- Noble Gases.8.1.7.10 Bases 3.11.2.3: Dose -Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Other Than Noble Gases Procedure Number:.Beaver Valley Power-Station .1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:*-5 .18 of 78 8.1.7.11 Bases 3.11.2.4: Gaseous Radwaste Treatment System 8.1.7.12 Bases 3.11.2.5: Gas Storage Tanks 8.1.7.13 Bases 3.11.4.1: Total Dose 8.1.7.14 Bases 3.12.1: REMP Program Requirements 8.1.7.15 Bases 3.12.2: REMP -Land Use Census 8.1.7.16 -Bases 3.12.3: REMP -Interlaboratory Comparison Program 8.1.8 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs (formerly; ODCM Appendix C)8.1.8.1 Controls 3.0.1 thru 3.0.4: Applicability 8.1.8.2 Controls 4.0.1 thru 4.0.4: Surveillance Requirements 8.1.8.3 Control 3.3.3.1: Radiation Monitoring Instrumentation 8.1.8.4 Control 3.3.3.9: Radioactive Liquid Effluent Monitoring Instrumentation 8.1.8.5 Control 3.3.3.10: Radioactive Gaseous Monitoring Instrumentation 8.1.8.6 Control 3.11.1.1: Liquid Effluent Concentration 8.1.8.7 Control 3.11.1.2: Liquid Effluent Dose 8.1.8.8 Control 3.11.1.3: Liquid Radwaste Treatment System 8.1.8.9 Control 3.11.1.4: Liquid Holdup Tanks 8.1.8.10 Control 3.11.2.1: Gaseous Effluent Dose Rate 8.1.8.11 Control 3.11.2.2: Dose- Noble Gases 8.1.8.12 Control 3.11.2.3: Dose -Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Other Than Noble Gases 8.1.8.13 Control 3.11.2.4: Gaseous Radwaste Treatment System 8.1.8.14 Control 3.11.2.5: Gas Storage Tanks 8.1.8.15 Control 3.11.4.1: Total Dose 8.1.8.16 Control 3.12.1: REMP Program Requirements 8.1.8.17 Control 3.12.2: REMP -Land Use Census Beaver Valley Power Station Procedure Number: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 19 of 79 8.1.8.18 Control 3.12.3: REMP -Interlaboratory Comparison Program 8.1.8.19 Control 6.9.2: Annual REMP Report 8.1.8.20 Control 6.9.3: Annual RETS Report 8.2 History Of ODCM Changes 8.2.1 Change (1) of BV-1 ODCM (Issue 1), Effective January, 1984 82.1.1 -This is the initial issue of the BV-1 ODCM, as prepared for implementation of the Radiological Effluent Technical Specifications (RETS). Implementation of this manual was commensurate with Amendment No. 66 to the Unit 1 Technical Specifications as approved by the NRC on March28, 1983.8.2.2 Change (2) of BV-1 ODCM (Issue 1, Rev 1), Effective October, 1984 8.2.2.1 A description of the changes implemented with this revision are as follows: 8.2.2.1.1 Section 1.0: Table 1.3-1 was revised to include liquid dose factors for nuclides presently identified at BVPS and not included in the original table.8.2.2.1.2 Section 2.0: Equations 2.1-19 and 2.1-22 were revised as approved at RSC Meeting No. BVPS-RSC-1-84 on January 31, 1984. The equations were revised to clarify flow rate terminology. 8.2.2.1.3 Section 2.0: Section 2.2.2 was revised to delete the food and ground pathways for gaseous dose rate calculations of 1- 131, tritium, and radionuclides in particulate form with half lives greater than 8 days.8.2.2.1.4 Section 2.0: Table 2.2-03 was revised to include 7 organs rather than only the maximum organ. Also, the receptor was changed from infant to child, and addition/deletion of nuclides to be consistent with the Technical Specifications and nuclides identified at BV-1.8.2.3 Change (3) of BV-1 ODCM (Issue 1, Rev 2), Effective July, 1986 8.2.3.1 A description of the changes that were implemented with this revision are as follows: 8.2.3.1.1 Section 1.0: Provide a flow based monitor setpoint adjustment factor in Section 1.1.2. This change makes Section 1.1.2 consistent with Section 1.1.1 and current procedures. 8.2.3.1.2 Section 1.0 and 2.0: Revise the 31-day dose projection limits and methodology in Sections 1.3.2, 2.3.1.2, and 2.3.2.2. This change corrected the 31-day dose projection limits and changed the dose projection methodology to be consistent with proposed software. Procedure Number:.Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: I/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 20 of78 S 8.2.3.1.3 Section 2.0: Revise the Gaseous Effluent Monitor Setpoints in Sections 2.1.1 and 2.1.2. They were revised due to pressure corrections determined for the detectors, changes in isotopic literature, and the addition of SPING Channel 5 alternate monitor data. The calculations supporting this item are contained in Calculation Packages ERS-SFL-85-031 and ERS-ATL-86-008.
8.2.4 Change
(4) of BV-1 ODCM (Issue 2), and BV-2 0DCM (Issue 1, Rev 1), Effective July, 1987 8.2.4.1 With the start-up of BV-2 in the second half of 1987, the BV-I ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows: 8.2.4.1.1 Produce functionally compatible BV-I and BV-2 ODCMs which address site dose rate limits and meet regulatory requirements. Note that due to the scope of the revisions to the Unit 1 ODCM, it was re-issued as Issue 2.Also, for clarity, the draft BV-2 ODCM previously submitted to the NRC was regarded as Issue I (historical) and operation of BV-2 began with Issue 1, Revision 1 of the BV-2 ODCM., 8.2.4.1.2 Section 1.0: A shared liquid radwaste system, permitting mixing of waste for processing, the sharing of dilution water, and the apportionment of dose according to NUREG-0133 was incorporated into both ODCMs.8.2.4.1.3 Section 2.0: A shared elevated gaseous radwaste system, permitting the mixing of gaseous radwaste and the apportionment of dose, according to NUREG-0133 was incorporated into both ODCMs.8.2.4.1.4 Section 2.0: Separate ground level gaseous releases were maintained. The BV-I ODCM :was updated to incorporate the B.V-2 five year meteorology base. Gaseous source terms were revised to that calculated for BV-I in the BV-2 FSAR, and terms were added for calculation of a turbine building release.8.2.4.1.5 Section 2.0: The gaseous effluent monitor alarm setpoints of both ODCMs were revised as required by revisions to meteorology, source terms, monitor efficiencies, and revised percentages of site dose rate limits.8.2.4.1.6 Section 2.0: Formal justification was provided for use of the "T" factor as described in the Containment Purge Dose Rate calculations. Whereas, the dose rate for a Containment Purge may be averaged over a time period not to exceed 960 minutes. Since the Containment air volume change time period is 60 minutes, then the maximum value for "T" is 16 (i.e., 960 minutes/60 minutes = 16). Procedure Number: Beaver Valley Power Station o /2-ODC-1.m1 Title: Unit: Level Of Use: ,1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 521 of 78 8.2.51 Change (5) of BV-I ODCM (Issue 2, Rev 1), and BV-2 0DCM (Issue 1, Revision 2), Effective December, 1987 8.2.5.1 Section 2.0: Sections 2.1.3 and 2.1.4 of both ODCMs were changed to delete a note concerning noble gas nuclides as requested by a NRC letter dated July 14,1987 titled Beaver Valley Unit 2 -Offsite Dose Calculation Manual, ODCM (TAC 63996).8.2.6 Change (6) of BV-1 ODCM (Issue 2, Rev 2), and BV-2 ODCM (Issue 1, Rev 3), Effective June, 1989 8.2.6.1 A description of the changes implemented with this revision are as follows: 8.2.6.1.1 Section 1.0 and 2.0: Both ODCMs were revised for addition of Sections 1.4 and 2.4. This addition gives a description of and includes flow diagrams of the Liquid Radwaste System and the Gaseous Radwaste System. (See justification 1)8.2.6.1.2 Section 1.0: Corrected typos to BV-I ODCM Equation 1.1-8 to show differentiation between the two fs, and add the division sign. (See Justification 1)8.2.6.1.3 Section 1.0: Re-define Fk in equation 1.3-1 of both ODCMs, as allowed by the NRC. (See Justification 1)8.2.6.1.4 Section 1.0 and 2.0: Typos were corrected to the following: (1) BV-1 ODCM equation 1.3-7; add a division sign between the brackets. (2) BV-1 ODCM equation 1.3-8; add a division sign between the brackets. (3)Equation 2.1-20 of both ODCMs; change the HHSP to HSP multiplier from 0.70 to 0.33. (4) Equation 2.1-24 of both ODCMs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1)8.2.6.1.5 Section 1.0 and 2.0: Typos were also corrected as follows: (1) Add the words "from each reactor unit" to five places (Sections 1.3.1, 1.3.2, 2.3.1.1, 2.3.1.2, and 2.3.2.2) of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (2) Correct punctuation in Section 2.3.2.1 of the BV-i ODCM. (3) Correct typos in Table 3.0-1 of both ODCMs. (4) Correct typos in Figure 3.0-3 of both ODCMs.8.2.6.1.6 Section 2.0: Add a Reference to Section 2 of the BV-1 ODCM. (See Justification 3)8.2.6.1.7 Section 2.0: Add the words "from the site" to Section 2.2.2 of both ODCMs.This ensures compliance with the current requirements of the Technical Specifications. (See Justification
- 2)
Procedure Number: Beaver Valley Power Station I :e/2-Nm Dr: 1 01 Title: Unit: Level Of Use: 1/2 General Skill Reference -ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 ~~22 of 7 8.2.6.1.8 Section 2.0: Revise BV-I ODCM Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit 1 Ventilation Vent and to correct a typo for Xe-135m in the Containment Vacuum Pumps. (See Justification 3)8.2.6.1.9 Section 2.0: Provide re-verified Pi, values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1)8.2.6.1.10 Section 2.0: Correct the definition for the tf value in the cow-meat pathway in Section 2.3.2.1 of both ODCMs. (See Justification 1)8.2.6.1T. 11 Section 2.0: Provide re-verified R values for the Beaver Valley site in Tables 2.3-2 through 2.3-20 of both ODCMs. (See Justification 1)8.2.6.1.12 Appendix B: Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3)8.2.6.2 The justification used for Change (6) to the ODCMs are as follows: 8.2.6.2.1 A letter dated March 2, 1989 (from the NRC) was~received by Duquesne Light regarding acceptance of the Offsite Dose Calculation Manuals. The NRC acceptance of the BV-I and BV-2 ODCMs was based on Technical Evaluation Reports (TER No. EGG-PHY-8194 and EGG-PHY-8217) provided by the Idaho National Engineering Laboratory. As stated in the letter, minor concerns are delineated in Section 4 of the TER.In general, these concerns are considered typos or additions and in one way impact any of the calculations currently being performed for dose contributions. However, one of these concerns is regarding the inability to reproduce the ODCM R values for the cow-meat, cow-milk and goat-milk pathways when using the ODCMINUREG-0 1:33 methodology. These R values (along with all other ODCM R values) were re-validated VIA Calculation Package No. ERS-ATL-89-014. The results of this package showed that the R values for the three aforementioned pathways were in error. SINCE the R values in error do not involve the controlling receptor for gaseous release (i.e.;the controlling receptor is VIA the Inhalation, Ground, and Vegetation pathways, not the pathways subject to error), THEN the changes will not adversely impact the accuracy or reliability of effluent dose calculations. 8.2.6.2.2 As requested by DLC letters ND3NSM:343:1, ND1NSM:3522, and NDINSM:3652, Technical Specifications were required to be verified in all plant implementing procedures. As part of this effort, wording errors/typos were identified in various sections of the ODCM.' This revision corrects the anomalies identified during the verification effort. Beaver Valley Power Station Procedure Number: Title:1!2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 523 of 79 8.2.6.2.3 As delineated in letter NDISHP:776, dated February 12, 1988 (BVPS-1 ODCM Table 2.2-2, Appendix B) a series of apparent discrepancies were identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation showed that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR expected release tables are based, is correct (i.e.; no credit was taken for routine filtration for Unit 1 releases). Except for revising the ODCM, no further corrective action is necessary because the particulates and iodines in the ODCM were not used for gaseous effluent alarm setpoint. Therefore, this change does not adversely impact the accuracy or reliability of setpoint calculations.
8.2.7 Change
(7) of BV-1 and 2 0DCM (Issue 3). Effective August, 1995 8.2.7.1 The combined ODCM contains the following changes: 8.2.7.1.1 Prior to ISSUE 3, BV- I and BV-2 had individual ODCMs that were generically equal. In an effort to simplify the implementing documents, the ODCMs have been combined. This merger of the individual ODCMs 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 Part 50. Also, this merger will not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. 8.2.7.1.2 Section 1.0: Revised Section 1.0 (Liquid Effluents) to show compliance with 10 CFR 20 Appendix B (20.1001 -20.240 1), Table 2, Col. 2 EC's. This includes the following: (1) Revising the alarm setpoints for monitors [RM-1LW-104, RM-1LW-116, and 2SGC-RQ1001. (2) Updating the BV-1 monitor detection efficiencies. (3) Updating discharge rate and dilution rate parameters for BV-I and BV-2. (4) Adding the alarm setpoints for monitors[RM-IRW-100, RM-IDA-100, 2SWS-RQ 101, and 2SWS-RQ 102]. Procedure Number: Beaver Valley Power Station 1o2-'ODC-1.m1 Title: Unit: Level Of Use: 1/2 General Skill Reference, .ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: *5 ~24 of7" 8.2.7.1.3 Section 1.0: Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseous Effluents) to merge the BV- 1 alarm setpoint calculations with the BV-2 alarm setpoint calculations. For all practical purposes, when Tables, Figures, and Equations were transferred to the combined ODCM, the numbering was kept generically equal. The two exceptions to this are as follows: (1) If a table was contained in both ODCMs, but each had data specific to BV-I or BV-2, then an a or b was added to the table. For example, Table 1.1-1 was previously included in the BV- 1 ODCM and the BV-2 ODCM. These tables are now numbered 1.1-1 a and I. 1 -l b denoting BV- 1 and BV-2 respectively. A cross reference for ODCM tables is provided in the Table Of Contents. (2) If an equation was contained in both ODCMs, but each had data specific to BV-I or BV-2, then a (1) or (2) was added to the equation. For example, Equation 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCM. These equations are now numbered 1.1 (1)- 1 and 1.1(2)- 1, denoting BV- I and BV-2 respectively. A cross reference for ODCM equations is provided in the Table Of Contents.8.2.7.1.4 Section 3.0: Revised Section 3.0 (Radiological Environmental Monitoring Program) to list the program requirements from the Radiological Assessment Branch Technical Position (Revision 1, 1979).8.2.7.1.5 Section 4.0: Revised Section 4.0 (Information Related To 40 CFR 190) to provide clarified reporting requirements for the Special Report. The clarifications were taken from Generic Letter 89-01, Supplement No. 1 (NUREG-1301). 8.2.7.1.6 Appendix A: Revised Appendix A to transfer the Batch Release dispersion parameters from Appendix A (Tables A-2 through A-5) to Section 2.3 (Tables 2.3-35 through 2.3-38). This revision was done for clarification. For example, all dispersionparameters are now included in one area of the ODCM.'8.2.7.1.7 Appendix C: This is a new Appendix to the ODCM. Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of the ODCM per Generic Letter 89-01 and Generic Letter 89-01, Supplement No. I (NUREG 1301).This Appendix also includes selected Definitions and Tables as delineated in the Technical Specifications (Section 1) and selected Applicability and Surveillance Requirement statements as delineated in the Technical Specifications (Section 3/4). These were added to Appendix C for reference purposes, even though they are currently described in the Technical Specification. 8.2.7.1.8 Appendix D: This is a new Appendix to the ODCM. The bases for ODCM Controls were transferred from the Bases Section of the Technical Specifications to Appendix D of the ODCM per Generic Letter 89-01. Procedure Number: Beaver Valley Power Station 1/2-ODC-I.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 5 25 of 78 8.2.7.1.9 Appendix E: This is a new Appendix to the ODCM. The Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Reportreporting requirements are listed in this appendix to the ODCM.8.2.7.1.10 There are three differences (i.e., non-editorial changes) in this ODCM revision when compared to the previous BV-l and BV-2 Technical Specifications. These are the only changes that are identified by revision bars. These differences are as follows: 8.2.7. 1. 10. 1 First Difference -LLD Definition Clarification is described as follows: (1) There was a sentence removed in the LLD Standard Deviation Definitions delineated in Appendix C Tables 4.11-1 and 4.11-2. This sentence stated: "In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium in milk samples).". (2) This sentence was removed by justification of NUREG-0472, Rev. 2 (i.e.., this revision to the NUREG removed the sentence from Tables 4.11-1 and 4.11-2). At BV-I and 2, there are no other radionuclides normally present in effluent samples.However, there is applicability to environmental LLD calculations due to the existence of other radionuclides in environmental samples. This sentence, therefore, will not be removed from Appendix C, Table 4.12-1. (3) Removal of the sentence from Appendix C, Tables 4.11-1 and'4.11-2 does not adversely impact the accuracy or reliability of current or past effluent LLD calculations. This change maintains 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 Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. (4) This change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2,in generic agreement with NRC guidance (i.e., NUREG-0472) and industry standard. Procedure Number:.Beaver Valley Power Station 1/2'ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference'. ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:5 :26 of 78 p 8.2.7.1.10.2 8.2.7.1.10.3 Second Difference -Change From Semi-Annual Report To Annual Report as follows: (1) The frequency of the Radioactive Effluent Release Report was changed from Semi-Annual to Annual. This change is justified by Federal Register, Rules And Regulations (Vol.57, No. 169, Monday, August 31, 1992), where as; 10 CFR Part 50.36a(a)(2) states, in part. "Each licensee shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months of operation.. .the time between submission of the reports must be no longer than 12 months..." (2) This change maintains 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 Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. Third Difference -Implementation Of New 10 CFR 20 is described as follows: (1) The definition for MEMBER(S) OF THE PUBLIC was revised to agree with the definition in 10 CFR 20.1003. (2) The definition for UNRESTRICTED AREA was modified from the definition that was in the Technical Specifications prior to transferring to the ODCM. This modification was necessary to ensure that the ODCM dose model, for gaseous releases is not affected. The modification involved adding the following sentence: "For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or waterway adjacent to or crossing the site that is not occupied continuously by MEMBER(S) OF THE PUBLIC". (3) The limits for liquid effluent concentration were changed from I times 10,CFR 20 Appendix B (20.1 -20.601), Table II, Col. 2 MPC's to 10 times 10 CFR 20 Appendix B (20.1001 -20.2401), Table 2, Col. 2 EC's.. This limit will now be referred to as the ODCM Effluent Concentration Limit (OEC). (4) For gaseous effluents, no changes.were made to implement the New 10 CFR 20.As justification, when the utility adopted the RETS (1/1/84), compliance to 10 CFR 20 shifted from the MPC concept to the Unrestricted Area Dose Rate concept. The Dose Rate concept is the preferred method of controlling gaseous effluent release rate, and will continue to be used in-lieu of the MPC or EC concept. (5) Changing to the OEC limit for liquid effluents accommodates needed operational flexibility to facilitate implementation of the New 10 CFR 20 requirements. (6) For information, the general intent of the New Part 20 is that radiation doses to members of the public not exceed 100 mrems per year, which is more restrictive than the 500 mrems per year limit in the Old Part 20, and that fuel cycle licensees also comply with 40 CFR 190. The New Part 20 does not include a requirement on I p Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:*5 .27 of 79 limiting radioactivity concentrations in effluents, which is less restrictive than the Old Part 20. (7) The basic requirements for RETS (i.e.; ODCM Appendix C Controls) are stated in 10 CFR 50.36a.These requirements indicate that compliance with the RETS will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the 10 CFR 20.106 (10 CFR 20.1302). These requirements also indicate that operational flexibility is allowed (with considerations for public health and safety) which may temporarily result in releases higher than such small percentages, but still within the MPC limits specified in the 10 CFR 20.106. The MPC's relate to an annual dose of 500 mrem. Also, 10 CFR 50.36a indicates that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents to ALARA as set forth in 10 CFR 50 Appendix I. (8) As stated in the Introduction to Appendix B of the New 10 CFR 20, the liquid EC's are based on an annual dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 mrem/year has been acceptable as a RETS limit for liquid effluents, it should not be necessary to reduce this limit by a factor often. (9) BV-1 and BV-2 has demonstrated that the use of the MPC's associated with the 10 CFR 20.106 has resulted in calculated maximum individual doses to a member of the public that are small percentages of the limits of 10 CFR 50 Appendix I. Therefore, the use of the OEC's, which correspond to an annual dose of 500 mrem (i.e.; 10 times the 10 CFR 20 EC's) should not have a negative impact on the ability to continue to -operate within the limits of 10 CFR 50 Appendix I, and 40 CFR 190. (10) Operational flexibility is also necessary in establishing a basis for effluent monitor setpoint calculations. As previously discussed, the EC's stated in 10 CFR 20 relate to a dose of 50 mrem in a year. This is too restrictive to base effluent monitor setpoint calculations. For many liquid effluent release situations, the monitor background is high, which could result in a monitor setpoint that is approximately equal to the monitor background. (11) In summary, to accommodate operational flexibility needed for effluent releases, the limits associated with the liquid release concentration (i.e.; the OEC)are based on 10 times the EC's stated in the 10 CFR 20. The multiplier of 10 is used because the annual dose of 500 mrem (10 CFR 20 MPC bases) is a factor of 10 higher than the annual dose of 50 mrem (10 CFR 20 EC bases). Compliance with the 100 mrem dose limit of the 10 CFR 20.1302 will be demonstrated by operating within the dose limits of 10 CFR 50 Appendix I, and 40 CFR 190 (which are also ODCM Controls for liquid and gaseous effluents). Implementation of the 10 CFR 20 for liquid effluents maintains 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 Part 50, and does not Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use:* 1/2 General Skill Reference_ ODCM: Index, Matrix and History of ODCM Changes Revision: IPage Number: o S adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. 8.2.7.2 In summary, Per Generic Letter 89-01, the transfer of RETS procedural details fulfills the goal of the USNRC Policy Statement for Technical Specification improvements. It is not the USNRC's (or DLC's) intent to reduce the level of radioactive effluent control. Rather, the intent is to provide programmatic controls for RETS (as delineated in Technical Specification 6.8.6) and allow for relocation of the procedural. details of the RETS to the ODCM.8.2.8 Change (8) of BV-1 and 2 ODCM (Issue 3, Rev 1), Effective October, 1995 8.2.8.1 A description of the changes implemented with this revision are as follows: 8.2.8.1.1 Index: Editorial changes were made for clarity. (See justification 1)8.2.8.1.2 Section 1.0: Revised Nb-95 and Nb-97 dose factors in Table 1.3-1 due to changing the niobium bioaccumulation factor. (see justification 2)8.2.8.1.3 Appendix A: A change was made to Table 1.1 so that the letter A would proceed the table number. (See justification 1)8.2.8.1.4 Appendix B: A descriptive paragraph was added at the front of this Appendix. Also, changes, were made to the tables so that the letter B would proceed the table numbers. (See justification 1)8.2.8.1.5 Appendix C: Descriptive paragraphs were added at the front of the Appendix (See justification 1). Removed the process flow rate operability and surveillance requirements for gaseous effluent radiation monitors [2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ1 12] from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the threegaseous effluent pathways to Tables 3.3-13 and 4.3-13 (See justification 4). Revised Surveillance Requirements 4.11.1.1.3 and 4.11.1.1.4 and notes e and g of Table 4.11-1 to clarify Turbine Building sump sampling requirements (See justification 5).8.2.8.1.6 Appendix D: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)8.2.8.1.7 Appendix E: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)8.2.8.1.8 Appendix F: This is a new Appendix to the ODCM. It contains plant procedure references for Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specification Procedure Matrix. (See justification 1)0 Beaver Valley Power Station PrUce:ure N2ODC.01 Title: : "Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 29 of 79 8.2.8.2 The justification used for change (8) to the ODCM are as follows: 8.2.8.2.1 These changes are considered editorial in nature. Therefore, these editorial changes 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. Also the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. 8.2.8.2.2 This change resulted from revising the bioaccumulation factor (BF) for niobium from the value posted in Table A- I of Regulatory Guide 1.109, Revision 1, 1977 (30,000 pCi/kg per pCi/l). Since this change in niobium BF (as documented and justified in Appendix A to Calculation Package No.ERS-ATL-83-027) merely removes the conservatism associated with organism uptake, then 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. Also, removing the conservatism will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. 8.2.8.2.3 This change removes the process flow rate operability and surveillance requirements for BV-2 Gaseous Effluent Radiation Monitors [2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQI 12] from Appendix C Tables 3.3-13 and 4.3-13. These items were removed from the ODCM by justification provided in Calculation Package No. ERS-ATL-90-02
- 1. A safety analysis and a no significant hazards evaluation were prepared and approved prior to submitted it to the NRC via TSCR No. 2A-61 in 1992. However, it was withdrawn in 1993 in an effort to alleviate any further delays associated with approval of TSCR No. IA-175/2A-37 (Generic Letter 89-01 implementation).
Removal of these requirements from the ODCM 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.Also removal of these items will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. The following is a summary of the justification. (1) BVPS-l and BVPS-2 is currently using, and will continue to use design (maximum) system flow rates in ODCM Dose & Dose Rate Calculations, rather than those flow rates observed during normal plant operation. (2) BVPS-2 UFSAR Section 11.3.3 indicates that the source term for these three pathways are not significant. These pathways are not included in UFSAR Tables 11.3-1 through 11.3-4 that list the expected and design releases for each potentially radioactive pathway. (3)The DLC commitment to Regulatory Guide 1.97, Rev. 2 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. This RG applies to instrumentation used during and after postulated accident conditions. These three process flow rate instruments were not used in any accident analysis, nor are they used .to assess plant conditions during and following an accident. (4) The DLC commitment to Regulatory Guide 1.21, Rev. 1 (Section 1.8-1 of the Beaver Valley Power Station Procedure Nur1/2-0 DC-1 0 1 Title: Unit: Level Of Use: 1/2 General Skill Referencef ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number.+ 5 30 of 78 BVPS-2 UFSAR) is not affected. RG 1.21, Section C.2 (Location of Monitoring) states in part: "All major and potentially significant paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences, should be monitored. Measurements of effluent volume, rates of release, and specific radionuclides should be made insofar as practical.. " As previously stated, the three process flow rate instruments are located on effluent pathways that do not have a significant source term. (5) BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicate that the building ventilation system for these three pathways are non-safety related and are not required to perform any safety-related function. (6)There is no effect to the Noble Gas Monitors located on these three pathways. The Noble Gas Monitors are still capable of performing their intended functions as described in BVPS-2 UFSAR Section 11.5.2.4.8.2.8.2.4 This change adds alternate system effluent flowrate measuring devices for the three BV-1 gaseous effluent pathways to Appendix C Tables 3.3-13 and 4.3-13. A 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by adding the alternate measuring devices to Appendix C Tables 3.3-13 and 4.3-13. This conclusion is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety. (2) There is no creation of a possibility for an accident or malfunction of a different type than any evaluated previously. (3) There is no reduction in the margin of safety. (4) Also, since this change merely adds alternate measuring devices that meet the same surveillance requirements of the primary channel, then 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. Also, addition of the alternate flow rate measuring devices will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. 8.2.8.2.5 This change to the ODCM clarifies Turbine Building sump sampling requirements and clarifies effluent related actions associated with detection of radioactivity in the secondary system. These clarifications are documented and justified in Calculation Package No. ERS-ATL-95-006. Also, since these clarifications were shown to meet the intent of NUREG-1301 (superseding NUREG-0472) and the BVPS- 1 and 2 UFSAR's, then the clarification 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. Also, the clarifications will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. Also, a 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by clarifying these actions. This conclusion is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety. (2) There is no creation of a possibility for an accident or malfunction of a different type Beaver Valley Power Station ProcedureNumber: 1/2-ODC- 1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 31 of 78 than any evaluated previously. (3) There is no reduction in the margin of safety.8.2.9 Change (9) of BV-1 and 2 ODCM (Issue 3, Rev 2), Effective May 1997 8.2.9.1 A description of the changes implemented with this revision are as follows: 8.2.9.1.1 Index: Editorial changes were made for clarity. (See Justification 1)8.2.9.1.2 Section 1.0: Clarifying statements were added to Tables 1.2-1a and 1.2-lb to show that the recirculation times listed are based on historical recirculation rates. Figure 1.4-3 was added to show BV-1 and 2 liquid Effluent Release Points. (See Justification 1)8.2.9.1.3 Section 3.0: Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest D/Q. (See Justification 2)8.2.9.1.4 Appendix C: Added plant specific Mark Numbers to Tables 3.3-12, 4.3-12, 3.3-13 and 4.3-13 (See Justification 1). Corrected typographical errors on Surveillance Requirement 4.11.4.1.1 (See Justification 1). Added clarifying statements from NUREG- 1301 and the Radiological Assessment Branch Technical Position to Tables 3.12-2 and 4.12-1 (See Justification 1).Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest D/Q (See Justification 2).8.2.9.1.5 Appendix E: Corrected typographical error on Table 6.9-1. (See Justification 1)8.2.9.1.6 Appendix F: Added procedure details to Tables 11, 12 and 13. (See Justification I)8.2.9.2. The justification used for Change (9) to the ODCM are as follows: 8.2.9.2.1 These changes are considered editorial in nature. The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. Beaver Valley Power Station Procedure Nu1m:ODC Title: Unit: Level Of Use: 1/2 General Skill Referen db.ODCM: Index, Matrix and History of ODCM Changes Revision: .Page Number, 1_5 32 of 78 8.2.9.2.2 This change removes the option to perform broad leaf vegetation sampling at the site boundary (in a sector with the highest D/Q) in lieu of the garden census. Per NUREG-1301 and the Radiological Branch Technical Position, this option does not apply to plants with elevated releases. Since BV-Il and 2 have elevated releases, the option should not be exercised. A review of past garden census showed that the option was never exercised at BV-I and 2.Since this change removes an option that should not be exercised, then 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. Also, removal of the option will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. 8.2.10 Change (10) of BV-1 and 2 ODCM (Issue 3, Rev 3), Effective June 1997 8.2.10.1 A description of the changes implemented with this revision are as follows: 8.2.10.1.1 Section 2.0: A release point for the BV-2 Turbine Building Vent was added (for editorial purposes) to Figure 2.4-2.8.2.10.2 The justification used for Change (10) to the ODCM is as follows: 8.2.10.2.1 This change is considered editorial in nature. The change adds an equivalent item that was previously located on BV-2 Technical Specification Figure 5.1-2. Since BV-2 Technical Specification Amendment 83 removed this figure, then the gaseous release point for the BV-2 Turbine Building Vent needed transferred' to the ODCM. Therefore, since this change is considered editorial, 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. Also, the editorial change will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. 8.2.11 Change (11) of BV-1 and 2 0DCM (Issue 3, Rev 4), Effective
- -March 1998 8.2.11.1 A description of the changes implemented with this revision are as follows: 8.2.11.1.1 Index: Editorial changes were made for clarity.8.2.11.1.2 Section 3.0: The distances for the environmental monitoring sample points'were revised to show a more accurate measurement from the center of the Unit 1 Containment Building.
The actual sample locations and descriptions remain unchanged. Also, the 4 individual quadrant maps showing TLD locations were consolidated into I map. This is a Corrective Action to Condition Report CR 980353. Procedure.Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 33 of 78 8.2.11.1.3 Section 4.0: Added clarifying statements as to how doses due to radioactive effluents for MEMBERS OF THE PUBLIC conducting activities inside the site boundary are derived and reported. This is a Corrective Action to Condition Report CR 971578.8.2.11.1.4 Appendix C: Added statements to Action 23 of Table 3.3-12 to clarify that batch liquid releases may also be initiated with the same Action needed for resuming the release. This is a recommendation from the 1997 RETS Self-Assessment. A note was also added to this table to clarify that independent signatures on the discharge permit satisfy the requirement for "two technically qualified members of the Facility Staff independently verify the release rate calculation..." Added Action 29 to RM-IGW-108B on Table 3.3-13. This addition ensures consistency with the other 7 continuous gaseous effluent pathway Actions for Noble Gas Monitor inoperability. Added plant specific Mark Numbers for primary and alternate instrumentation to Tables 3.3-13 and 4.3-13 as follows: (1) For Noble Gas Activity Monitors, [RM-1VS-109 Channel 5] was added as an alternate to[RM-IVS-101B] and [RM-1VIS-1 10 Channel 5] was added as an alternate to [RM-1VS-107B]. [RM-IGW-109 Channel 5] was not added as an alternate to [RM-IGW-108B] at this time, because it does not perform on auto-isolation of gaseous waste decay tank release upon upper activity alarm.(2) For Particulate Activity Monitors, [RM-1VS-109 Channel 1] was added as an alternate to [RM-1 VS-101A], [RM-1VS- 1110 Channel 1] was added as an alternate to [RM-VS-I 107A], and [RM- IGW- 109 Channel 1 ] was added as an alternate to RM- 1GW- 108A.8.2.11.1.5 Appendix E: Corrected typographical errors on Table E:6.9-1 8.2.11.1.6 Appendix F: Updated the procedure details for primary and alternate instrumentation included in Appendix C Tables 3.3-13 and 4.3-13. Reducedýthe amount of detail contained in reference to the Operating Manual L-5 logs so that the position of the surveillance on the logs can be changed without having a need to change the Tables in this Appendix. This is a Corrective Action to Condition Report CR 980129.8.2.11.2 The justification used for Change (11) to the ODCM is as follows: 8.2.11.2.1 These changes are considered editorial in nature. The changes either correct.typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations. Beaver Valley Power Station ProcedureN,1 DC Title: Unit: Level Of Use: 1/2 General Skill Reference,- ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: -5 34 of 78 8.2.12 Change (12) of BV-1 and 2 ODCM (Issue 3, Rev 5), Effective November 1998 8.2.12.1 A description of the changes implemented with this revision are as follows.8.2.12.1.1 Index: Editorial changes were made for clarity. (See Justification 1.)8.2.12.1.2 Section 1.0: Added clarification for calculation of radionuclide concentration when the Post Dose Correction Factor is >1. (See Justification 1).8.2.12.1.3 Section 3.0: Added an additional site location for the upstream-environmental surface water sample. Added additional method after collecting and compositing this sample. (See Justification 2.)8.2.12.1.4 Appendix C: Revised the definitions for MEMBER(S) OF THE PUBLIC and UNRESTRICTED AREA to ensure compliance with 10 CFR 20.1003.'(See Justification 1.) Added a definition for MEMBER(S) OF THE PUBLIC to ensure compliance with 40 CFR 190.02(k). (See Justification 1.)Added plant specific Mark Numbers for primary and alternate instrumentation to Table 3.3-13 that were inadvertently omitted from change (11) to the ODCM. (See Justification 1.) Added clarification to Table 4.11-2 as to where and when H-3 samples of Waste Gas Storage Tanks are to be V obtained. This is a Corrective Action to Condition Report CR 981489. (See Justification 1.) Added clarification to note "e" of Table 4.11-2 as to the appropriate ventilation release path. This is a Corrective Action to CR 981490. (See Justification 1.). Corrected an obvious omission on Table 3.12-1 to ensure that 2 TLD's are used for determination of Direct Radiation.(See Justification 1.) Incorporated the appropriate changes to Table 3.12-1 that are described above for Section 3.0. (See Justification 2.)8.2.12.1.5 Appendix F:Added procedure details from the Chemistry Manual to Table 6. This is a Corrective Action to Condition Report CR 981488. (See Justification 1.) .8.2.12.2 The justifications used for Change (12) to the ODCM are as follows: 8.2.12.2.1 These changes are considered editorial in nature. The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations. Beaver Valley Power S tation Procedure Number: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 IGeneral Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 5 of 78 8.2.12.2.2 These changes involve the upstream environmental surface water sample method and sample site. Since these changes were shown to meet the intent ofNUREG-1301, and BVPS-1 and 2 UFSAR's, then 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.Also, the change will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations. Also, a 10 CFR 10.50 safety evaluation has concluded that no unreviewed safety question is involved by adding an additional sample site and sample method. This evaluation is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important -to safety.(2) There is no creation of a possibility for an accident or malfunction of a different type than any evaluated previously. (3) There is no reduction in the margin of safety.8.2.13 Change (13) of BV-1 and 2 ODCM (Issue 3, Rev 6), Effective May 1999 8.2.13.1 A description of the changes implemented with this revision are as follows: 8.2.13.1.1 Index: Editorial changes were made for clarity.8.2.13.1.2 Section 3.0: Updated figure number and table reference. Removed a redundant upstream environmental surface water sampling location.8.2.13.1.3 Appendix C: Made editorial changes for clarity. Added definitions for SHUTDOWN and STARTUP. Changed definition for ODCM to ensure agreement with definition provided in Unit 1/2 Technical Specification Amendments 220/97. Changed designations for primary and alternate instruments on Tables 3.3-12, 4.3-12, 3.3-13 and 4.3-13 from "P" and "A" to"Pri" and "Alt". Clarified use of the Flow Rate Measurement Devices for the Cooling Tower Blowdown Line on Tables 3.3-12 and 4.3-12 .to show that the Unit 1/2 combined instrument [FT-1CW-101-1] is the primary and both of the individual Unit I and Unit 2 instruments [FT-I CW- 101] and [2CWS-FT101] are the alternates. Updated Actions 24, 25 and 26 of Table 3.3-12 to describe use of comparable alternate monitoring channels when the primary channels are INOPERABLE. Clarified Table 3.3-13 Action 28 applicability for Unit 2 gaseous effluent monitors. Clarified Table 3.3-13 Action 30 to show that applicability is for batch purges of the reactor containments. Changed reference of Special Report compliance requirement from Technical Specification 6.9.2f to 10 CFR 20.2203 and 10 CFR 50.4 as permitted by Unit 1/2 Technical Specification Amendments 220/97.Clarified note b of Table 4.11-2 regarding sampling and surveillances frequencies. Clarified Controls 3.12.1 and 3.12.2 to ensure compliance with NUREG-1301. Beaver Valley Power. Station Prcedure Number/2DC.1 Title: Unit: ILevel Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number 1 5 .36of 78 8.2.13.1.4 Appendix E: Made editorial changes for clarity. Changed reference of Special Report compliance requirement from Technical Specification 6.9.2f to 10 CFR 20.2203 and 10 CFR 50.4 as permitted by Unit 1/2 Technical Specification Amendments 220/97. Changed submittal date of annual REMP report from May I to May 15 as permitted by Unit 1/2 Technical Specification Amendments 220/97. Changed column heading in Table E: 6.9-1 to ensure consistency with NUREG-1301. 8.2.13.2 The justification used for change (13) to the ODCM is as follows: 8.2.13.2.1 All changes are considered editorial in nature. The changes either clarify the intent of the original specification or add equivalent items form the standard guidance document (NUREG- 1301) or recent Technical Specification Amendments. Therefore, since these changes are considered editorial, the changes 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. Also, the editorial changes will not adversely impacttheaccuracyor reliabilityofeffluentdose orsetpoint calculations.
- 8.2.14 Change (14) of BV-1 and 2 ODCM (Rev 14), Effective March 2000 8.2.14.1 Prior to this ODCM change, the change numbers did not match the Issue and Revision numbers. For example, the last implemented ODCM change was (13), but carried an Issue 3, Revision 6 designation.
Therefore, as of this ODCM change (14), consecutive Revision numbers will begin with Revision 14.8.2.14.2 A description of the changes implemented with this revision are as follows: 8.2.14.2.1 Index: Editorial changes were made for clarity.. References to condition reports CR 982097, CR 992652 and CR 993021: were added.8.2.14.2.-2 Appendix C: Editorial changes were made for clarity. Corrected a typographical error on Table 3.3-12 in regards to FT-CW-101-1. Changed the grab sampling requirement from 8 hours to 12. hours for Table 3.3-12 Action 24 (NUREG-1301, Table 3.3-12, Action 36 and 37 allow this change). Enhanced the Channel Functional Test requirements on Table 4.3-12 from Q(6) to Q(1) for RM-l DA- 100 (Corrective Action to Condition Report CR 99302 1). Add clarification to Table 3.3-13 and 4.3-13 to show the plant specific Mark Numbers for the primary and alternate BV-I Sample Flow Rate Measuring Devices. Corrected a typographical error on Table 3.3-13 Action 27. Separated Action 28 of Table 3.3-13 into individual Action 28 requirements for System Effluent Flow Rate Measuring Devices/Process Flowrate Monitors and individual Action 28 requirements for Sample Flow Rate Measuring Devices/Sample Flowrate Monitors.Added clarification to Table 3.3-13 to show that Action 29 and Action 32 are applicable for continuous releases. Added an alternate method in lieu of Beaver Valley Power Station Procedure Number:* I/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 37 of 78 grab sample collection (ie., local monitor readings can be obtained when communication is lost to the Control Room) to show compliance to Table 3.3-13 Action 29. Changed the grab sampling requirement from 8 hours to 12 hours for Table 3.3-13 Action 29 and Action 32 (NUREG- 1301, Table 3.3-013, Action 47 allows this change). Corrected typographical errors on Table 4.11-1 in regards to liquid composite analysis frequency and table notation.8.2.14.2.3 Appendix F: Made editorial changes for clarity. Updated the procedure details for primary and alternate instrumentation included in Appendix C Tables 3.3-13 and 4.3-13. Added appropriate references to the HP Shift Logs (ie., HPM Appendix 1) when these logs are used satisfy ODCM Appendix C Surveillances and Actions (Corrective Action to Condition Report CR 992652).8.2.1-4.3 The justification used for change (14) to the ODCM is as follows: 8.2.14.3.1 Most of these changes are considered editorial in nature. All changes were screened for i 0CFR50.59 applicability. In summary, the BVPS-l and 2 UFSAR's are not impacted, because the changes either clarify the intent of the original specification, add plant specific Mark Numbers, or add equivalent items from the standard guidance document (NUREG- 130 1).Therefore, these changes will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, 10 CFR50.36a, and Appendix I to I0CFR50. Also, these changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations. 8.2.15 Change (15) of BV-1 and 2 ODCM (Rev 15), Effective August 2000 8.2.15.1 A description of the changes implemented with this revision are as follows: 8.2.15.1.1 Index: Editorial changes were made for clarity. Reference to Condition Report CR 001682 was added. Reference to NRC unresolved Item 83-30-05 was added.8.2.15.1.2 Appendix C: Editorial changes were made for clarity. Annotated Actions 28 of Table 3.3-13 into Action 28A and 28B to show differentiation between Action 28A requirements for system/process flow rate measurement and Action 28B requirements for sampler flow rate measurement. Added an alternate method in lieu of 4 hour flow rate estimations (ie; assume ODCM design values for system/process.flow rate) to show compliance with Table 3.3-13 Action 28A when the system/process flow rate monitor is inoperable. Annotated Actions 30 of Table 3.3-13 into Action 30A and 30B to show differentiation between Action 30A requirements for BV- 1 reactor containment purges and Action 30B requirements for BV-2 reactor containment purges. Beaver Valley Power Station ProcedureN,,mro
- l...... I/2 ODC-10 Title
- Unit: Level Of Use:..1/2 General Skill Reference,:-
ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:...._ __5 38 of 78 8.2.15.2 The justification used for change (15) to the ODCM is as follows: 8.2.15.2.1 Some of these changes are considered editorial in nature. These changes were screened for 1OCFR50.59 applicability and determined not to impact the BVPS-1 and 2 UFSAR's. Since the editorial changes clarify the intent of the original specification, then these changes will maintain the level of radioactive effluent control required by 1OCFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to IOCFR50. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. 8.2.15.2.2 The change to allow use of design (maximum) system flow rates in lieu of 4 hour flow rate estimations (for five of the eight gaseous effluent release pathways) was screened for lOCFR50.59 applicability and determined not to impact the BVPS- I and 2 UFSAR's. The 4 hour flow rate estimations for these effluent release pathways have never been used in ODCM Dose and Dose Rate Calculations. The method for use of process flow rates in ODCM Dose and Dose Rate Calculations remains unchanged. For example, BVPS-1 and BVPS-2 is currently using, and will continue to use design (maximum)system flow rates in ODCM Dose and Dose Rate Calculations for all eight gaseous effluent release pathways. This is necessary to ensure that DLC W response to NRC Unresolved Item 50-334/83-30-05 is not compromised. Also this change is considered similar and within the justification provided for ODCM change (8) that removed all of the process flow rate operability and surveillance requirements for the other three gaseous effluent release pathways. Based on the above, these'changes will maintain the level of radioactive effluent control required by I OCFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to I0CFR50. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. 8.2.16 Change (16) of BV-1 and 2 oDCM,(Effective April 2002)8.2.16.1 A description of the changes implemented with this revision are as follows: 8.2.16.1.1 The entire BV- I and 2 ODCM was converted to the ODC format as delineated in 1/2-ADM-0 100. As part of this process, the ODCM was separated into eight procedures as follows: 8.2.16.1.1.1 1/2-ODC-1.01, Rev 0; ODCM: Index, Matrix and History of ODCM Changes (formerly; ODCM Index and Appendix F)8.2.16.1.1.2 1/2-ODC-2.01. Rev 0; ODCM: Liquid Effluents (formerly; ODCM Section 1 and 5) Beaver Valley Power Station Procedure Numbr: 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5- 39 of 79 8.2.16.1.1.3 8.2.16.1.1.4 8.2.16.1.1.5 8.2.16.1.1.6 8.2.16.1.1.7: 8.2.16.1.1.8 1/2-ODC-2.02, Rev 0; ODCM: Gaseous Effluents (formerly; ODCM Section 2 and 5)1/2-ODC-2.03, Rev 0; ODCM: Radiological Environmental Monitoring Program (formerly; ODCM Section 3)1/2-ODC-2.04, Rev 0; ODCM: Information Related to 40CFR190 (formerly; ODCM Section 4)1/2-ODC-3.01, Rev 0; ODCM: Dispersion Calculational Procedure and Source Term Inputs (formerly; ODCM Appendix A & B)1/2-ODC-3.02, Rev 0; ODCM: Bases for ODCM Controls (formerly; ODCM Appendix D)1/2-ODC-3.03, Rev 0; ODCM: Controls for RETS and REMP Programs (formerly; ODCM Appendix C and E)8.2.16.1.2 Procedure 1/2-ODC-3.02, Rev 0: Technical Specification Bases 3/4.3.3.1 was duplicated in the Bases for ODCM Controls as permitted by Unit 1/2 Technical Specification Amendments I A-246/2A-124.(368)8.2.16.1.3 Procedure 1/2-ODC-3.03, Rev 0: Portions of Technical Specification LCO 3.3.3.1 (including portions of Tables 3.3-6 and 4.3-3) were transferred to the ODCM Controls as permitted by Unit 1/2 Technical Specification Amendments 1A-246/2A-124.(3.2.6.
- 8) Specifically, this includes the Mid and High Range Channels of Noble Gas Effluent Monitors [RM- 1 VS- 109 (7 and 9), RM-1VS-110 (7 and 9), RM-1GW-109 (7 and 9), and 2HVS-RQ109C and 109D], the Atmospheric Steam Dump Valve/Code Safety Relief Valve Discharge Monitors [RM-1 MS-IOOA, B and C] and Auxiliary Feedwater Pump Turbine Exhaust Monitor [RM-IMS-101].
The Preplanned Method of Monitoring (PMM) was' also added for clarification of necessary actions when the primary instrument is inoperable. Addition of the PMM's are considered an editorial change because it merely specifies the asset number (or appropriate form number), which were included as PMM's in previously approved station documents. 8.2.16.1.4 Procedure 1/2-ODC-3.03, Rev 0: Added clarifications to ODCM Control 3.33.9 Table 3.3-13 to show that Action 30A and Action 3B are applicable to the initial batch purge of the reactor containment atmosphere. All other releases of reactor containment atmosphere (i.e.; after the initial batch purge)are considered continuous releases. Procedure Number: Beaver Valley Power Station 1°/2-ODC" 1.01 Title: Unit: Level Of Use: 1./2 General Skill Reference Title:on t PaeNmbr ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number 5 40 of 78 8.2.16.1.5 Procedure 1/2-ODC-3.03, Rev 0: Added specific plant asset numbers to ODCM Control 3.3.3.10 Table 3.3-13 and Table 4.3-13 to show that Sample Flow Rate Monitor flow transmitters [2HVS-FIT1O1-1, 2RMQ-FIT301-1, 2HVL-FIT1 12-1 and 2RMQFIT303-1] may be used as comparable alternates when the pirimary instruments [RM- I1 Monitor Item 28 for 2HVS-RQ 101, 2RMQ-RQ301, 2HVL-RQ1 12 and 2RMQ-RQ303], respectively, are INOPERABLE. This is considered an editorial change because the primary monitoring channel (i.e.; RM-1 1 Monitor Item 28) display already receives its input from these same flow transmitters. 8.2.16.1.6 Procedure 1/2-ODC-3.03, Rev 0: Added notation to ODCM Control 3.3.3.10 Table 3.3-13 and Table 4.3-13 to show that [RM-1GW-109 Channel 5] may be used as a comparable alternate to [RM- 1GW-108B] for continuous releases. However, since [RM-iGW-109 Channel 5] cannot perform an automatic isolation of gaseous waste decay or storage tank releases, then notation was also added to prevent using this monitor as a comparable alternate for batch releases. This is considered an editorial change because it merely specifies the asset number of a redundant alternate monitoring channel that, was included in previously approyed station documents. 8.2.16.1.7 Procedure 1/2-ODC-3.03, Rev 0: Replaced the requirements for "Particulate Activity Monitors" in ODCM Control 3.3.3.10 Tables 3.3-13 and Table 4.3-13 with requirements for "Particulate and Iodine Samplers". This is considered an editorial change because the NRC guidance document used for preparation of ODCM Controls (NUREG- 1301) contains the clarification that the requirements listed in these Tables are for the "Particulate and Iodine Samplers", and not for the "Particulate Activity Monitors". 8.2.16.2 The justification used for change (16) to the ODCM is as follows: 8.2.16.2.1 The specific radiation monitoring channels transferred to the ODCM provide alarms and indications to alert plant personnel of high radiation conditions and to assist in evaluating and trending plant effluents. The Actions applicable if the monitors are inoperable require only that area surveys be performed on a daily basis, or that explanations of inoperability be provided in an annual effluent report. The Actions do not impact or reference the operability of other systems nor do the Actions require that plant operation be terminated at any time.8.2.16.2.2 Some of the radiation monitoring effluent monitors transferred to the ODCM provide indications used to assess selected plant parameters following an accident consistent with the recommendations of NUREG-0737. However, the monitors do not provide indication for post accident variables that have been identified as Regulatory Guide 1.97 Type A or Category I. Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and-History of ODCM Changes Revision: Page Number: 5 41 of 78 8.2.16.2.3 The Safety Analysis performed for the License Amendments conclude that the radiating monitoring channels transferred to the ODCM do not reduce the effectiveness of the requirements being relocated. Rather, the transferred results in a change in the regulatory control required for future changes made to the requirements. The requirements will continue to be implemented by the appropriate plant procedures in the same manner as before, However, future changes to the transferred requirements will be controlled in accordance with 10 CFR 50.59 instead of requiring a license amendment per 10 CFR 50.90.8.2.16.2.4 Based on the above, these changes 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. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. 8.2.17 Change (17) of BV,1 and 2 OCDM (Effective August 2002)8.2.17.1 A description of the changes implemented with this revision are as follows: 8.2.17.1.1 Procedure 1/2-ODC-3.03, Rev 1: Technical Specification LCO 3.11.1.4 for Liquid Storage Tank Activity Limits, and LCO 3.11.2.5, for Gas Storage Tank Activity Limits were transferred to ODCM Controls 3.11.1.4 and 3.11.2.5 respectively as permitted by Unit 1/2 Technical Specification Amendments IA- 250/2A-130.(3.2. 6.9)8.2.17.1.1.1 8.2.17.1.1.2 As part of the preparation work for transfer of the Liquid Storage Tank Activity Limits to the ODCM, the 10 Curie Limit for these tanks was re-verified and documented in Calculation Package ERS-ATL 007.(3.2.3.9) The results of this calculation provide tank specific activity limits to ensure that the 1OCFR20 Appendix B Table 2, Col. 2 EC Limits will be maintained should an accidental release of the tank(s)contents occur. Previously, LCO 3.11.1.4 used a generic limit of 10 Curies for each of the four tanks listed. However, formal documentation for derivation of the 10 Curie value could not be located in the records storage system.In addition, individual tank Activity limits were developed for the Unit 1 and 2 Refueling Water Storage Tanks (RWST's), which were also added to this ODCM Control. The Surveillance Requirements for determination of RWST Activity will not be performed once per 7 days like the other Liquid Storage Tanks, because radioactive material is not added to the RWST's on a weekly basis. Therefore, the surveillance for determination of (RWST's) Activity will be performed within 7 days of returning reactor cavity water (radioactive material)back to the RWST (i.e.; during a refueling outage). Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference. ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number W 1 5 42 of 78 8.2.17.1.2 Procedure 1/2-ODC-3.03, Rev 1: Changed the due date of the Annual Radioactive Effluent Release Report from April l1to May 1 as permitted by Unit 1/2 Technical Specification Amendments 1A-250/2A-130.(3.2.6.9) 8.2.17.1.3 Procedure 1/2-ODC-3.03, Rev 1: Changed Table 3.3-12 of Control 3.3.3.9 to correct an obvious omission of Channel Operability and Action Statement Requirements for Flow Rate Measurement Device [FR- 1LW- 103] on the Liquid Waste Containment Drain Line. This obvious omission is detailed in CR 02-05533 .22.12)8.2.1. 1.4 Procedure 1/2-ODC-3.03, Rev 1: Made editorial changes to correct the primary asset numbers of the BVPS-2 Sample Flowrate Monitors as shown on Tables 3.3-13 and 4.3-13 of Control 3.3.3.10. These changes clarify that the primary Sampler Flowrate Monitor is the device that is used for monitoring sample flowrate through the Particulate and Iodine Sampler Flowpath, not the Particulate and Iodine Monitoring Flowpath.8.2.17.2 The justification used for change (17) of the ODCM is as follows: 8.2.17.2.1 These changes merely transfers existing storage tank activity limits from the Technical Specification to the ODCM and changes the due date for the Annual Radioactive Effluent Release Report as permitted by Unit 1/2 Technical Specification Amendments IA-250/2A-130. As part of this change, the ODCM Control for Liquid Storage Tank Activity Limits was enhanced to add ODCM Controls and Surveillance Requirements for the Unit 1 and Unit 2 RWST's. Therefore, these changes (as delineated in the Technical Specification Amendments) 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. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. 8.2.18 Change (18) of the BV- Iand 20DCM (Effective October 2002)8.2.18.1 A description of the changes implemented with this revision are as follows: 8.2.18.1.1 Procedure 1/2-ODC-3.03, Rev 2: Added requirement for applicable station groups notification of pending ODCM changes as described in CR 09-05711 .(3.2.2.13) 8.2.18.2 The justification used for change (18) of the ODCM is as follows: 8.2.18.2.1 This change is considered editorial in nature, which exempts the change from Regulatory Applicability Determination. Therefore, this change will not impact the level of radioactive effluent control required by 1OCFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to 1OCFR50. Also this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. Beaver Valley Power Station ProcedroeNumber: ~1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:-1 5 43 of 78 8.2.19 Change (19) of BV-1 and 2 0DCM (Effective November 2002)8.2.19.1 A description of the changes implemented with this revision are as follows: 8.2.19.1.1 Procedure 1/2-ODC-2.01, Rev 1: Changed Table 1. 1-la and 1.1-1b to add Zn-65 to the respective BV- 1 and 2 Liquid Source Term as described in CR 02-06174 (CA-01, CA-13 and CA-14). For information, zinc may be added to the reactor, coolant system in an effort to reduce general corrosion of primary system materials and mitigation of stress corrosion cracking. Added benefits to zinc addition involve preferential release of nickel and cobalt which, in-turn, reduces plant dose rates. Development of the specific Zn-65 Annual Release Activity is delineated in Calculation Package No. ERS-ATL-83_027.(3.2.3.1) Addition of Zn-65 to the source terms also caused changes in the Liquid Effluent Monitor Alarm Setpoints, and appropriate monitor conversion factors.8.2.19.1.2 Procedure 1/2-ODC-2.01, Rev 1: Table 1.1-la was changed to update the remainder of the source term with annual release values derived in Stone and Webster Calculation Package No. UR(B)- 160.(3 2 3'0)8.2.19.1.3 Procedure 1/2-ODC-2.01, Rev 1: Editorial changes were made to this procedure for update of ODCM references and to add discussion of why Liquid Waste Evaporators are no longer used at BV- 1 and 2 to process liquid waste.8.2.19.2 The justification used for change (19) of the ODCM is as follows: 8.2.19.2.1 Addition of Zn-65 to the BV-1 and 2 Liquid Source Terms, along with update of the BV- 1 and 2 Liquid Source Term is considered a procedure correction, and is enveloped by the Regulatory Applicability Determination performed for BV-1 ECP-02-04
- 10. Based on the above, these changes 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.Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.20 Change (20) of BV-1 and 2 0DCM (Effective October 2003)8.2.20.1 A description of the changes implemented with this revision are as follows: 8.2.20.1.1 Procedure 1/2-ODC-2.01, Rev 2: Changed LW System diagrams (Attachment D) to indicate the flow path for cross connect of LW between Unit 1 and Unit 2.8.2.20.1.2 Procedure 1/2-ODC-2.02, Rev 1: Changed Table 2.1-1 to revise the source term for the Unit 1 Containment Vacuum Pumps as described in CR03-04830 (CA-03). Beaver Valley Power Station J Title: Unit: Level Of Use: 1/2 General Skill Reference --ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 8.2.20.1.3 Procedure 1/2-ODC-3.03, Rev 3: Changed the Preplanned Method of Monitoring (PMM) in Attachment D Table 3.3-6 and Table 4.3-3.Specifically, the 2nd PMM for the Reactor Building/SLCRS Mid & High Range Noble Gas Monitors (RM-1VS-I 10 Ch 7 & Ch 9) was changed FROM "(RM-1VS-107B)" TO "(RM-1VS-107B,'or RM-1VS-1 10 Ch 5)".Also, the 2nd PMM for the Auxiliary Building Ventilation System Mid &High Range Noble Gas Monitors (RM-1VS-109 Ch 7 & Ch 9) was changed FROM "(RM-I VS-101B)" TO "(RM-I VS- 01B, or RM-1 VS-109 Ch 5)".Similarly, the 2nd PMM for the'Gaseous Waste/ Process Vent System Mid &High Range Noble Gas Monitors (RM-IGW-109 Ch 7 & Ch 9) was changed FROM "(RM- IGW-108B)" TO "(RM-I GW- 108B, or RM- 1GW- 109 Ch 5)".8.2.20.1.4 Procedure 1/2-ODC-3.03, Rev 3: Changed Attachment J Control 3.11.1.4 to update the activity limits for the liquid storage tanks to the values specified in Calculation Package No. ERS-ATL-95-007. 8.2.20.1.5 Procedure 1/2-ODC-3.03, Rev 3: Changed Attachment K Table 4.11-2 to add more specific guidance for sampling of Gaseous Effluent Pathways.Specifically, this table is generic for Unit 1 & Unit 2 Gaseous Effluent Pathways, but sampling may only need required at some of the Gaseous Effluent Pathways rather than all of the Gaseous Effluent Pathways (as could W be inferred from the wording in the Table Notation). Therefore to prevent unnecessary sampling, applicability statements were added to this table to delineate which ventilation systems are affected by the note(s). Also, note (f) includes a clarification of how compliance to this requirement is achieved per response to NRC Unresolved Item 50-334/83-30-05. 8.2.20.2 The justifications used for change (20) of the ODCM are as follows: 8.2.20.2.1 Procedure 1/2-ODC-2.01. Rev 2: Changing the diagram to show the LW cross connect between Unit I and Unit 2 is not a change to plant configuration, and is considered a procedure correction. Specifically, this procedure of the ODCM already describes the shared radwaste treatments system. Also, the UFSAR's describe the cross connect. Based on the above, this 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 Ito 10 CFR 50. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. Beaver Valley Power Station Procedure Nuir:ODC101 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 5 45 of 78 8.2.20.2.2 Procedure 1/2-ODC-2.02, Rev 1: The original source-term calculation for the GW System was based on an operating flow rate of 5 scfm for the Unit 1 containment vacuum pumps. The flow rate for the new pumps is 70 scfm.Consequently, the source-term was revised per Calculation Package ERS-HHM-87-014 and then transcribed to this procedure. Although the new pumps represent a factor of 15 increase in flow rate, the gaseous effluent monitor alarm setpoints are unchanged. Specifically, the previous setpoints were based on a percentage of Offsite Dose; Rate Limits, and those values were actually above the range of the instruments, so an on-scale value was substituted. This is also true for the re-calculated setpoints, so the same on-scale values are used. In summary, changing the source term is considered a procedure correction, and is enveloped by the Regulatory Applicability Determination performed for BV-1 ECP-02-0079. Based on the above, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. .This procedure change implements a Corrective Action per CR03-04830-03. 8.2.20.2.3 Procedure 1/2-ODC-3.03, Rev 3: Changing the Preplanned Method of Monitoring (PMM) will prevent unnecessary grab sampling (ie; the 3rd PMM) when the primary channel for the Mid or High Range Noble Gas Monitor is inoperable. Specifically, IF other Noble Gas Monitoring channels are available on that effluent pathway, THEN monitoring should be assumed with those channels as the 2nd PMM. In summary, the 3rd PMM (ie; obtaining grab gas samples every 12 hours) should only be performed as a last resort to a complete lack of continuous noble gas monitoring channels being available on that effluent pathway. Based on the above, this 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.Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.. This procedure change implements a Corrective Action per CR03-06123-01. 8.2.20.2.4 Procedure 1/2-ODC-3.03, Rev 3: Changing the activity limits for liquid storage tanks does not affect original plant accident analyses. Specifically, the original analyses were performed in accordance with NUREG-0800 SRP 15.7.3 using the best available data at that time. The updated analyses were also performed in accordance the same NUREG, but current (more accurate)data was used to, determine allowable activity content in each tank. Based on the above, this 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 Ito 10 CFR 50. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR03-07487-05. Procedure Number:, Beaver Valley Power Station 1/2-ODC-I.01 Title: Unit: Level Of Use: 1/2 ,General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 ~46 of 7 8.2.20.2.5 Procedure 1/2-ODC-3.03, Rev 3: Changing Attachment K Table 4.11-2 to add more specific guidance for sampling of Gaseous Effluent Pathways is considered a simple change. Specifically, this change merely prevents unnecessary sampling of unaffected ventilation pathways. Based on the above, this 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., Also, this change will not impact the accuracy or reliability of effluefit dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR03-06281-01. 8.2.21 Change (21) of BV-1 and 2 ODCM (Effective November 2004)8.2.21.1 A description of the changes implemented with this revision are as follows: 8.2.21.1.1 Procedure 1/2-ODC-1.01, Rev 4, Procedure 1/2-ODC-2.01, Rev 3 and Procedure 1/2-ODC-3.03, Rev 4: Changed ownership of procedures from the: Radiation Protection Section to the Nuclear Environmental & Chemistry Section per CR05-01169-14, CR05-01169-15 and CR05-01169-21. 8.2.21.1.2 Procedure 1/2-ODC-2.01, Rev 3: Changed Attachment D to correct the volume of Liquid Waste Drain Tanks (2LWS-TK21A/21B) from 7,500 , gal/tank to 10,000 gal/tank.8.2.21.1.3 Procedure 1/2-ODC-3.03, Rev 4: Changed Attachment C to implement the increased flexibility in Mode restraints that is described in LAR 1 A-321/2A-193 and CR03-09288-19. 8.2.21.1.4 Procedure 1/2-ODC-3.03, Rev 4: Corrected a typographical error in Attachment 0, Control 3.11.2.5 per CR03-11726-01. Specifically, the final word in Action (a) was changed from "nad" to "and".8.221.1.5 Procedure 1/2-ODC-3.03, Rev 4: Revised Attachment F, (Table 3.3-13 and 4.3-13) to correct'a typographical error per CR04-01643-01. Specifically, the Asset Number for the Vacuum Gauge used for measurement of sample flow (from the Alternate Sampling Device) was changed from [PI-IGW-13] to [PI-1GW-135]. 8.2.21.1.6 Procedure 1/2-ODC-3.03, Rev 4: Revised Attachment F, (Table 3.3-13 and*4.3-13) per CR04-02275-01. Specifically, clarification was provided to indicate that the "Sampler'Flow Rate Monitors are the devices used for"Particulate and Iodine Sampling". 8.2.21.1.7 Procedure 1/2-ODC-3.03, Rev 4: Revised Attachment J, Control 3.11.1.4, ACTION a, to add clarification that requires specific calculation of 10 CFR Part 20 EC's when the individual tank limits are exceeded.8.2.21.2 The justifications used for change (21) of the ODCM are as follows: ...Beaver Valley Power Station Procedure Number: Power S1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 47 of 78 8.2.21.2.1 Procedure 1/2-ODC-1.01, Rev 4, Procedure 1/2-ODC-2.01, Rev 3 and Procedure 1/2-ODC-3.03, Rev 4: Changing ownership of these procedures from Radiation Protection to Nuclear Environmental & Chemistry is considered a procedure correction. SINCE the changes merely transfers RETS, REMP and ODCM responsibilities to a different manager, THEN the changes 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. Also, the changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. The procedure changes implement Corrective Actions per CR05-01169-14, CR05-01169-15, and CR05-01169- '21.8.2.21.2.2 Procedure 1/2-ODC-2.0 1, Rev 3: Changing the, volume of the Unit 2 Liquid Waste Tank is considered a procedure correction. SINCE this was a typographical error on the Attachment, THEN it does not impact the actual tank volume that is used in effluent release calculations and offsite dose determinations. Therefore, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. 8.2.21.2.3 Procedure 1/2-ODC-3.03, Rev 4: Changing Attachment C to implement the increased flexibility in Mode restraints (described in LAR IA-321/2A-193) is considered a simple change. SINCE the change implements guidance provided in the Technical Specifications, THEN 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR03-09288-19. 8.2.21.2.4 Procedure 1/2-ODC-3.03, Rev 4: The typographical error in Attachment 0, Control 3.11.2.5 is considered a procedure correction. Therefore, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR03 -11726-0 1. lProcedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: j Level Of Use: 1/2 I General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: .,.. Page Number: 4.... ...... ...._5 __48 of_78 8.2.21.2.5 Procedure 1/2-ODC-3.03, Rev 4: Correcting the typographical error in Attachment F, (Table 3.3-13 and 4.3-13) is considered a procedure correction. SINCE this change merelycorrects an obvious error, THEN this change will maintain the level of radioactive effluent control required by 10 CFR 20A1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR04-01643-01. 8.2.21.2.6 Procedure 1/2-ODC-3.03, Rev 4: Providing clarification for the Sampler Flow Rate Monitors is considered a simple change, because it was possible to misinterpret which filter paper sampler (e.g.; moving filter or fixed filter)the specification was referring to. SINCE no changes were made to actual samplers used for effluent release calculations or offsite dose determinations, THEN this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR04-02275-0 I.8.2.21.2.7 Procedure 1/2-ODC-3.03, Rev 4: Providing clarification that requires calculation of 10 CFR Part 20 EC's (when the individual tank limits are exceeded) is considered a simple change. Specifically, the individual tank limits were derived from an assumed source-term and may not be representative of the actual source term at time of sample. This clarification also ensures that a "Special Report" is submitted only when the 10 CFR Part 20 EC limits are actually exceeded (i.e.; when calculated using actual sample analysis) at the nearest surface water supply and the nearest potable water supply in the unrestricted area. Per Calculation Package No. ERS-ATL 007 (32.3.9), the nearest surface water supply and the nearest potable water supply are considered to be the entrance to the Midland Water Treatment Facility. SINCE no changes were made to the bases for the tank activity limits, THEN this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. BeaveIrValley Power Station. Procedure Number: 1/2-ODC-I.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: Rs5 49 of 78 8.2.22 Change (22) of BV-1 and 2 ODCM (Effective August 2006)8.2.22.1 A description of the changes implemented with this revision are as follows: 8.2.22.1.1 Procedure 1/2-ODC-2.01, Rev 4: Incorporated Improved Technical Specification Reference changes from T.S. 6.8.6 to T.S. 5.5.2, per CR05-03306. Revised the alarm setpoints of [RM-1RM-100] and [RM-1DA-100] via vendor calculation Package No. 8700-UR(B)-223. These changes reflect the Extended Power Uprate (EPU) at Unit I per ECP-04-0440, Unit 1 TS Amendment No. 275 and CR06-04908-03. Updated the figure of Liquid Effluent Release Points (Attachment D, Figure 1.4-3) to incorporate a modified version of Plant Drawing No. 8700-RM-27F per CR05-03854-01. 8.2.22.1.2 Procedure 1/2-ODC-2.02, Rev 2: Changed ownership of procedure from the Radiation Protection Section to the Nuclear Environmental & Chemistry Section per CR05-01169-16. Incorporated a "<" designation for all low range noble gas effluent monitor alarm setpoints to meet the provisions of vendor calculation Package No. 8700-UR(B)-223. These changes reflect the Extended Power Uprate (EPU) at Unit 1 per ECP-04-0440, Unit 1 TS Amendment No. 275 and CR06-04908-04. 8.2.22.1.3 Procedure 1/2-ODC-3.03, Rev 4: Revised the alarm setpoints of the mid range and high range noble gas effluent monitors via vendor calculation Package No. 8700-UR(B)-223. These changes reflect the Extended Power Uprate (EPU) at Unit 1 per ECP-04-0440, Unit 1 TS Amendment No. 275 and CR06-04908-03. 8.2.22.2 The justifications used for change (22) of the ODCM are as follows: 8.2.22.2.1 Procedure 1/2-ODC-2.01, Rev 4: Updating the alarm setpoints and the figure of liquid effluent release points are considered procedure corrections, because they merely update the ODCM to agree with previously approved documents that were implemented with TS Amendments. SINCE the change merely updates the ODCM, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. SINCE PORC review & acceptance is required per TS 6.14 and 1/2-ADM- 1640, THEN the review is considered complete per Regulatory Applicability Determination RAD-06-03831, RAD-06-01658 and RAD-06-05070. As previously noted, these procedure changes implement Corrective Actions per CR06-04908-03, and CR05-03854-01. Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 BeaverVally _General__Skill _ ._Title: Unit: Level Of Use: 1/2 IGeneral Skill Reference,-. ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number. W 8.2.22.2.2 Procedure 1/2-ODC-2.02, Rev 2: Changing the ownership of the procedure and updating the alarm setpoints with a "<"designation are considered procedure corrections, because they merely update the ODCM to agree with previously approved documents that were implemented with TS Amendments. SINCE the change merely updates the ODCM, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. SINCE PORC review & acceptance is required per TS 6.14 & 1/2-ADM-1640, THEN the review is considered complete per Regulatory Applicability Determination RAD-06-03831 and RAD-06-01658. As previously noted, these procedure changes implement Corrective Actions per CR05-01169-16 and CR06-04908-04. 8.2.22.2.3 Procedure 1/2-ODC-3.03, Rev 4: Updating the alarm setpoints is considered a procedure correction, because this merely updates the ODCM to agree with previously approved documents that were implemented with TS Amendments. SINCE the change merely updates the ODCM, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. SINCE PORC review & acceptance is required per TS 6.14 & 1/2-ADM- 1640, THEN the review is considered complete per Regulatory Applicability Determination RAD-06-03831 and RAD-06-01658. As previously noted, these procedure changes implement Corrective Actions per CR06-04908-03. 8.2.23 Change (23) of BV-1 and 2 ODCM (Effective December 2006)8.2.23.1 A description of the changes implemented with this revision are as follows: 8.2.23.1.1 Procedure 1/2-ODC-1.01, Rev 5: Changed Attachment C, Table F: 3a of the procedure, matrix to add Form 1/2-ENV-01.04.FOI as documentation for performing a Channel Functional Test of the Unit I Primary and Alternate Gaseous Effluent Sampler Flowrate Measuring Devices per CR04-09895. Attachment C Tables were also changed to denote transition of ODCM Channel Checks from Operations (L5 Logs) to Nuclear Environmental &Chemistry (Form 1/2-ADM-0606.FOI & F02) pet CR05-01422. Also, per Improved Technical Specifications (ITS), changed Attachment C Tables to reflect change in term from CHANNEL FUNCTIONAL TEST to CHANNEL OPERATIONAL TEST (COT), and added step 4.1.2 to identify requirements for ODCM changes record review and retention requirements. Revised step 5.3 to require ODCM changes be reviewed and accepted by PORC per CR05-03306. Procedure Number: Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCMChanges Revision: Page Number: 5 51 of 78 8.2.23.1.2 Procedure 1/2-ODC-2.01, Rev 5: Revised the alarm setpoints of [2SWS-RQ 101 ]via vendor calculation Package No. 10080-UR(B)-508. These changes reflect the Extended Power Uprate (EPU) at Unit 2 per ECP-04-0441, Unit 2 TS Amendment No. 156 and CR06-6476-0 1.8.2.23.1.3 Procedure 1/2-ODC-2.03, Rev 1: Updated the existing REMP sampling locations, with the most recent survey results that were performed using a Global Positioning System per CR05-01390-02. 8.2.23. lA Procedure 1/2-ODC-3.02, Rev 2: Changed ownership of procedure from the Radiation Protection Section to the Nuclear Environmental & Chemistry Section per CR05-01169-20. 8.2.23.1.5 Procedure 1/2-ODC-2.03, Rev 1, Procedure 1/2-ODC-2.04, Rev 1 and Procedure 1/2-ODC-3.01, Rev 1: Changed ownership of procedures from the Radiation Protection Section to the Nuclear Environmental & Chemistry Section per CR05-01169-17, CR05-01169-18 and CR06-01169-19. 8.2.23.2 The justifications used for change (23) of the ODCM are as follows: 8.2.23.2.1 Procedure 1/2-ODCl.01, Rev 5: Changing Attachment C, Table F: 3a of the procedure matrix to add Form 1/2-ENV-01.04.F01 as documentation for performing the Channel Functional Test of the Unit 1 Primary and Alternate Gaseous Effluent Sampler Flowrate Measuring Devices is considered a procedure correction, because no Acceptance Criteria was altered.Transition of ODCM Channel Checks from Operations (L5 Logs) to Nuclear Environmental & Chemistry (Form 1/2-ADM'0606.FOI & F02) is also considered a procedure correction, because the no Acceptance Criteria was altered. SINCE these changes merely correct the procedure matrix, THEN the changes 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. As previously noted, these procedure changes implement Corrective Actions per CR04-09895, CR05-01422 and CR05-03306. Procedure Number: Beaver Valley Power Station 1 :/2-ODC-1.01 Title: Unit; Level Of Use: 1/2 General Skill Reference. ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: " I 5 I 52 of 78 8.2.23.2.2 Procedure 1/2-ODC-2.0i, Rev 5: Updating the alarm setpoints is considered a procedure correction, because this merely updates the ODCM to agree with previously approved documents that were implemented with TS Amendments. SINCE the change merely updates the ODCM, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. SINCE PORC review & acceptance is required per TS 6.14 & 1/2-ADM-1640, THEN the review is considered complete per Regulatory Applicability Determination RAD-06-04585. As previously noted, these procedure changes implement Corrective Actions per CR06-6476-0 1.8.2.23.2.3 Procedure 1/2-ODC-2.03, Rev 1: Updating the existing REMP sampling locations with the most recent survey results that were performed using a Global Positioning System is considered a procedure correction. SINCE the change provides more accurate distances to existing REMP sampling locations, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. The procedure change implements Corrective Actions per CR04-00149-12 and CR05-01390-02.8.2.23.2.4 Procedure 1/2-ODC-2.03, Rev 1, Procedure 1/2-ODC-2.04, Rev 1 and Procedure 1/2-ODC-3.0i, Rev 1: Changing ownership of these procedures from Radiation Protection to Nuclear Environmental & Chemistry is considered a procedure correction. SINCE the changes merely transfers RETS, REMP and ODCM responsibilities to a different manager, THEN 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. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. These procedure changes implement Corrective Actions per CR05-01169-17, CR05-01 169-18 and CR06-01169-19.-END - Procedure Number: Beaver Valley Power Station 1/2-ODC-l.0O Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 53 of 78 ATTACHMENT A Page 1 of 6 LIST OF ODCM TABLES LIQUID EFFLUENTS Included in Procedure 1/2-ODC-2.01 1.1-la BV-1 Liquid Source Term 1.1-lb BV-2 Liquid Source Term 1.2-la BV-1 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks 1.2-lb BV-2 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks 1.3-1 Ai. Values For An Adult For The Beaver Valley Site GASEOUS EFFLUENTS Included in Procedure 1/2-ODC-2.02 2.1-Ia BV-I Radionuclide Mix For Gaseous Effluents 2.1-lb BV-2 Radionuclide Mix For Gaseous Effluents 2.1-2a BV- I Monitor Detector Efficiencies 2.1-2b BV-2 Monitor Detector Efficiencies 2.2-1 Modes Of Gaseous Release From Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50 2.2-2a BV-1 Radionuclide Mix For Gaseous Effluents 2.2-2b BV-2 Radionuclide Mix For Gaseous Effluents 2.2-3 Distances Of Limiting Maximum Individual Receptors To Release Points For Annual x/Q Values ANNUAL AVERAGE X/Q Included in Procedure 1/2-ODC-2.02 2.2-4 BV-1 And 2 Containment Vents (Ground Release)2.2-5 BV-1 And 2 Ventilation Vents (Ground Release)2.2-6 BV-1 And 2 Process Vent (Elevated Release)2.2-7 BV-1 And 2 Turbine Building Vents (Ground Release)2.2-8 BV-2 Decontamination Building Vent (Ground Release) Beaver Valley Power Station P1oce0ur1Number.,.... 12 ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index,' Matrix and History of ODCM Changes Revision: Page Number " 5 54 of 78 ATTACHMENT A Page 2 of 6 LIST OF ODCM TABLES 2.2-9 BV-2 Waste Gas Storage Vault Vent (Ground Release)2.2-10 BV-2 Condensate Polishing Building (Ground Release)NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS Included in 1/2-ODC-2.02 2.2-11 Dose Factors For Noble Gases And Daughters 2.2-12 Dose Parameters For Finite Elevated Plumes, Beaver Valley Site P&I DOSE PARAMETERS Included in 1/2-ODC-2.02 2.2-13 Pit Values For A Child For The Beaver Valley Site MODES OF GASEOUS RELEASES Included in Procedure 1/2-ODC-2.02 2.3-1 Modes Of Gaseous Release From The Beaver Valley Site Vents For Implementation Of 10 CFR20And10 CFR50 P&I ORGAN DOSE FACTORS Included in 1/2-ODC-2.02 2.3-2 R Values for Inhalation -Adult 2.3-3 R Values for Inhalation -Teen 2.3-4 R Values for Inhalation -Child 2.3-5 R Values for Inhalation -Infant 2.3-6 R Values for Ground 2.3-7 R Values for Vegetation -Adult 2.3-8 R Values for Vegetation -Teen 2.3-9 R Values for Vegetation -Child 2.3-10 R Values for Meat -Adult 2.3-11 R Values for Meat -Teen 2.3-12 R Values for Meat -Child 2.3-13 R Values for Cow Milk -Adult 2.3-14 R Values for Cow Milk -Teen Beaver Valley Power Station Procedure Number: B1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: ATTACHMENT A Page 3 of 6 LIST OF ODCM TABLES 2.3-15 R Values for Cow Milk -Child 2.3-16 R Values for Cow Milk -Infant 2.3-17 R Values for Goat Milk -Adult 2.3-18 R Values for Goat Milk -Teen 2.3-19 R Values for Goat Milk -Child 2.3-20 R Values for Goat Milk -Infant CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 Miles) Included in Procedule 1/2-ODC-2.02 2.3-21 BV-1 And 2 Process Vent (Elevated Release)2.3-22 BV-1 And 2 Containment Vents (Ground Release)2.3-23 BV-1 And 2 Ventilation Vents (Ground Release)2.3-24 BV-1 And 2 Turbine Building Vents (Ground Release)2.3-25 BV-2 Condensate Polishing Building (Ground Release)2.3-26 BV-2 Decontamination Building Vent (Ground Release)2.3-27 BV-2 Waste Gas Storage Vault Vent (Ground Release)CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) Included in Procedure 1/2-ODC-2.02 2.3-28 BV-1 And 2 Process Vent (Elevated Release)2.3-29 BV-1 And 2 Containment Vents (Ground Release)2.3-30 BV-1 And 2 Ventilation Vents (Ground Release)2.3-31 BV-1 And 2 Turbine Building Vents (Ground Release)2.3-32 BV-2 Condensate Polishing Building (Ground Release)2.3-33 BV-2 Decontamination Building Vent (Ground Release)2.3-34 BV-2 Waste Gas Storage Vault Vent (Ground Release) Y Beaver Valley Power Station ProcedureNumber: Title: Unit: Level Of Use: 1/2 General Skill Reference ,".ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 5 56 of7" ATTACHMENT A Page 4 of 6 LIST OF ODCM TABLES BATCH RELEASE DISPERSION PARAMETERS (Special Distances) Included in Procedure 1/2-ODC-2.02 2.3-35 BV-1 And 2 Containment Vents (Ground Release)2.3-36 BV-I And 2 Ventilation Vents (Ground Release)2.3-37 BV-1 And 2 Process Vent (Elevated Release)BATCH RELEASE DISPERSION PARAMETERS (0-5 Miles) Included in Procedure 1/2-ODC-2.02 2.3-38 BV-I And 2 Process Vent (Elevated Release)ENVIRONMENTAL MONITORING Included in Procedure 1/2-ODC-2.03 3.0-1 Radiological Environmental Monitoring Program DISPERSION CALCULATION Included in Procedure 1/2-ODC-3.01 A: 1 BV-1 And 2 Release Conditions INPUTS TO COMPUTER CODES Included in Procedure 1/2-ODC-3.01 B: 1a Inputs To GALE Code For Generation Of BV-I Liquid Source Term Mixes B: lb Inputs To SWEC LIQ 1BB Code For Generation Of BV-2 Liquid Source Term Mixes B:2a Inputs To SWEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes B:2b Inputs To SWEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes ODCM CONTROLS Included in Procedure 1/2-ODC-3.03 C: 1.1 Operational Modes C: 1.2 Frequency Notation C:3.3-6 Radiation Monitoring Instrumentation C:4.3-3 Radiation Monitoring Instrumentation Surveillance Requirements C:3.3-12 Radioactive Liquid Effluent Monitoring Instrumentation C:4.3-12 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirementsp C:3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: ATTACHMENT A Page 5 of 6 LIST OF ODCM TABLES C:4.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements C:4.11-1 Radioactive Liquid Waste Sampling And Analysis Program C:4.11-2 Radioactive Gaseous Waste Sampling And Analysis Program C:3.12-1 Radiological Environmental Monitoring Program C:3.,12-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples C:4.12-1 Maximum Values For The Lower Limits Of Detection (LLD)FORMAT FOR ANNUAL REPORT Included in Procedure 1/2-ODC-3.03 E:6.9-1 Environmental Radiological Monitoring Program Summary ODCM CONTROLS PROCEDURE MATRIX Included in Procedure 1/2-ODC- 1.01 F:la BV-1 Radiation Monitoring Instrumentation Surveillance F: lb BV-2 Radiation Monitoring Instrumentation Surveillance F:2a BV-I Liquid Effluent Monitor Surveillances F:2b BV-2 Liquid Effluent Monitor Surveillances F:3a BV-1 Gaseous Effluent Monitor Surveillances F:3b BV-2 Gaseous Effluent Monitor Surveillances F:4 BV-1 and 2 Liquid Effluent Concentration Surveillances F:5 BV-1 and 2 Liquid Effluent Dose Surveillances F:6 BV-1 and 2 Liquid Effluent Treatment Surveillances F:7 BV-l and 2 Liquid Storage Tank Activity Limit Surveillances F:8 BV-1 and 2 Gaseous Effluent Dose Surveillances F:9 BV-1 and 2 Gaseous Effluent Air Dose Surveillances F: 10 BV-1 and 2 Gaseous Effluent Particulate and Iodine Dose Surveillances F: 11 BV-I and 2 Gaseous Effluent Treatment Surveillances Beaver Valley Power Station rocedureumber:2 C.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: *,S ATTACHMENT A Page 6 of 6 LIST OF ODCM TABLES F: 12a BV-1 Gaseous Storage Tank Activity Limit Surveillances F: 1 2a BV-2 Gaseous Storage Tank Activity Limit Surveillances F: 13 BV-1 and 2 Total Dose Surveillances F:14 BV-1 and 2 REMP Surveillances F: 15 BV-i and 2 Land Use Census Surveillances F: 16 BV-1 and 2 Interlaboratory Comparison Program Procedure Number: Beaver Valley Power Station 1/2-ODC-l.0l Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 -59 of 78 ATTACHMENT B Page 1 of 1 LIST OF ODCM FIGURES LIQUID EFFLUENTS Included in Procedure 1/2-ODC-2.01 1.4-1 1.4-2 1.4-3 5-1 GASEOUS BV-I Liquid Radwaste System BV-2 Liquid Radwaste System BV-I and 2 Liquid Effluent Release Points Site Boundary. For Liquid Effluents EFFLUENTS Included in Procedure 1/2-ODC-2.02 2.4-1 BV-1 and 2 Gaseous Radwaste System 2.4-2 BV-1 and 2 Gaseous Effluent Release Points 5-1 Site Boundary For Gaseous Effluents RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Included in Procedure 1/2-ODC-2.03 3.0-1 3.0-2 3.0-3 3.0-4 3.0-5 3.0-6 Air Sampling Locations TLD Locations Shoreline Sediment, Surface Water, And Drinking Water Sampling Locations Milk Sampling Locations Foodcrop Sampling Locations Fish Sampling.Locations -Procedure Number: Beaver Valley Power Station 1/2dODC-1.r1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number j 5
- 60of 78 a ATTACHMENT C Page [of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 RADIATION MONITORING INSTRUMENTION SURVEILLANCES TABLE F: Ia 1/2-ODC-3.03, Attachment D Control 3.3.3.1: Maintain Radiation Monitoring Channels in Table 3.3-6 OPERABLE APPLICABILITY:
MODES 1 thru 4 ODCM SR DESCRIPTION PROCEDURE 4.3.3.1 Test Monitors at Table 4.3-3 Frequency 4.3.3.1.1 Noble Gas Effluent Monitors -NOTE: Actions for INOPERABLE Monitors are documented SPINGS in the Operations & Rad Effluent Shift Logs.4.3.3.1.1.a Supplementary Leak Collection and 1MSP-43.59-1: Channel Calibration Release System Form. 1/2-ADM-0606.FO1: Channel Check (RM-1VS-110 CH7 & CH9) 1OST-43.07: [CTS] Channel Functional Test [ITS] Channel Operational Test (COT)4.3.3.1.1.b Auxiliary Building Ventilation System IMSP-43.60-1: Channel Calibration (RM-1VS-109 CH7 & CH9) Form 1/2-ADM-0606.FO1: Channel Check S1OST-43.07: [CTS] Channel Functional Test [ITS] COT 4.3.3.1.1.c Process Vent System (RM-1GW-109 1MSP-43.58-1: Channel Calibration CH7 & 9) Form 1/2-ADM-0606.FO1: Channel Check 1 OST-43.07: [CTS] Channel Functional Test [ITS] COT 4.3.3.1.2 Noble Gas Steam Effluent NOTE: Actions for INOPERABLE Monitors are documented Monitors in the Operations & Rad Effluent Shift Logs.4.3.3.1.2.ci Atmospheric Steam Dump Valve and 1MSP-43.62-1: RM-1MS-100A Channel Calibration
- v. 1.2a Code Safety Valve Discharge 1MSP-43.63-1:
RM-1MS-100B Channel Calibration (RM-1MS-100A, B, C) 1MSP-43.64-1: RM-1MS-100C Channel Calibration Form 1/2-ADM-0606.FO1: Channel Check 1OST-43.05: [CTS] Channel Functional Test [ITS] COT 4.3.3.1.2.b Auxiliary Feedwater Pump Turbine , 1MSP-43.65-h: Channel Calibration Exhaust (RM-1 MS-1 01) Form 1/2-ADM-0606.FOI: Channel Check 1OST-43.05: [CTS] Channel Functional Test [ITS] COT 4 II Beaver Valley Power Station Procere "Number:~1/2-ODC-I.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 61 of 78 ATTACHMENT C Page 2 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 RADIATION MONITORING INSTRUMENTION SURVEILLANCES TABLE F: lb 1/2-ODC-3.03, Attachment D Control 3.3.3.1: Maintain Radiation Monitoring Channels in Table 3.3-6 OPERABLE APPLICABILITY: MODES 1 thru 4 ODCM SR DESCRIPTION PROCEDURE 4.3.3.1 Test Monitors at Table 4.3-3 Frequency 4.3.3.1.1 -Noble Gas Effluent Monitors NOTE: Actions for INOPERABLE Monitors are documented in the Operations & Rad Effluent Shift Logs.4.3.3.1.2. Supplementary Leak Collection and 2MSP-43.33-1: Channel Calibration c.i.1..a Release System (2HVS-RQ109C & D) Form 1/2-ADM-0606.F02: Channel Check I _ I_ ,2OST-43.08: [CTS] Channel Functional Test (ITS] COT Procedure Number -Beaver Valley Power Station Pr2'Nu C4.. .Title: Unit: Level Of Use: 1/2 General Skill Reference,.- ODCM: Index,.Matrix and History of ODCM Changes Revision: Page.Number" 5 62 of 78 S ATTACHMENT C Page 3 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-I LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F: 2a 1/2-ODC-3.03, Attachment E Control 3.3.3.9: Maintain Liquid Effluent Monitors in Table 3.3-12 OPERABLE APPLICABILITY: During Releases Through The Flow Path ODCM SR DESCRIPTION PROCEDURE, 4.3.3.9 Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1 Monitors Providing Alarm and NOTE: Actions for INOPERABLE monitors are documented in the Automatic Termination .Operations & Rad Effluent Shift Logs.4.3.3.9.1.a Dquid Radwaste Effluent Line iMSP-43.18-h: Channel Calibration'(RM-1LW-104) Form 1/2-ENV-05.04.F01: Source Check 1/20M-17.4A.D: Source Check 1OST-43.09: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.FO1: Channel Check 4.3.3.9.1.b Liquid Waste Contaminated Drain Line 1MSP-43.23-1: Channel Calibration (RM-1LW-116) Form 1/2-ENV-05.04.FO1: Source Check 1/20M-17.4A.D: Source Check 1OST-43.09: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.FO1: Channel Check 4.3.3.9.1.c Auxiliary Feed Pump Bay Drain Monitor 1MSP-43.70-h: Channel Calibration (RM-IDA-100) 1OM-54.3 L5 Log: Source Check 1OST-43.09: [CTS] Channel Functional Test [ITS] COT Form 112-ADM-0606.FO1: Channel Check 43392 Monitors Providino Alarm. but Not NOTE: Actions for INOPERABLE monitors are documented in the Prividing Auto Termination Operations & Rad Effluent Shift Logs.4.3.3.9.2.a Component Cooling -Recirculation iMSP-43.10-I: Channel Calibration Spray Hx River Water Monitor 1OST-43.09: [CTS] Channel Functional Test [ITS] COT (RM-1RW-100) 10ST-43.09A: Source Check Form 1/2-ADM-0606.FOI: Channel Check 4.3.3.9.3 Flow Rate Measurement Devices NOTE: Actions for INOPERABLE monitors are documented in the ,Operations & Rad Effluent Shift Logs and 1/2-ENV-05.04 4.3.3.9.3a,b Liquid Radwaste Effluent Lines IMSP-17.05-h: Channel Calibration (3b)3a: (FR-1LW-104 for RM-1LW-104) 1MSP-17.06-1: F-LW-104-1 Channel Calibration (3a)3b: (FR-1LW-103 for RM-iLW-116) 1MSP-17.07-h: F-LW-104-2 Channel Calibration (3a)1MSP-17.08-1: F-LW-104-1 [CTS] Channel Functional Test [ITS] COT (3a)1MSP-17.09-1: F-LW-104-2 [CTS] Channel Functional Test [ITS] COT (3a)1MSP-1 7.10-I: F-LW-1 03 [CTS] Channel Functional Test [ITS] COT (3b)Form 1/2-ADM-0606.FOf: Channel Check 4.3.3.9.3.c Cooling Tower Blowdown Line 1MSP-31.04-I: F-CW-101 Channel Calibration (FT-i CW-101) 1MSP-31.05-1: F-CW-101 [CTS] Channel Functional Test [ITS] COT (FT-iCW-101-1) 1MSP-31.06-I: F-CW-101-1 Channel Calibration IMSP-31.07-h: F-CW-101-1 [CTS] Channel Functional Test [ITS] COT 1OM-54.3 L5 Log: FT-CW-101 Channel Check 1 OM-54.3 L5 Log: FT-CW-101-1 Channel Check 4.3.3.9.4 Tank Level Indicating Devices NOTE: Actions for INOPERABLE monitors are documented In the Operations Shift Logs 4.3.3.9.4.a Primary Water Storage Tank iMSP-8.01-h: L-PG115A [CTS] Channel Functional Test [ITS] COT (LI-1PG-1l15A for 1BR-TK-6A) 1 MSP-8.03-1: L-PG 15A Channel Calibration _ _ _ _ _ _1 OM-54.3 L5 Log: Channel Check (When Adding to Tank)4.3.3.9.4.b Primary Water Storage Tank (LI-1 PG-1i15B for 1 BR-TK-6B)1 MSP-8.02-h: L-PG- 15B [CTS] Channel Functional Test [ITS] COT 1MSP-8.04-1: L-PG-115B Channel Calibration IOM-54.3 L5 Loo: Channel Check (When Addina to Tankl 4.3.3.9.4.c Steam Generator Drain Tank (LI-1 LW-1 10 for 1 LW-TK-7A)1MSP-1 7.01-1: L-LW1 10 [CTS] Channel Functional Test [ITS] COT IMSP-1 7.03-1: L-LW1 10 Channel Calibration 1 OM-54.3 L5 Log: Channel Check (When Adding to Tank)I 4.3.3.9.4.d Steam Generator Drain Tank 1MSP-17.02-1: L-LWI11 [CTS] Channel Functional Test [ITS] COT (LI-1LW-111 for 1LW-TK-7B) 1MSP-17.04-1: L-LW111 Channel Calibration I_ I I OM-54.3 L5 Log: Channel Check (When Adding to Tank) Beaver Valley Power'Station Procedure Number: Power S1/2-ODC-1.01 Title: Unit: Level Of Use: I/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: I 5 63 of 79 ATTACHMENT C Page 4 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F: 2b 1/2-ODC-3.03. Attachment E Control 3.3.3.9: Maintain Liquid Effluent Monitors in Table 3.3-12 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR DESCRIPTION PROCEDURE 4.3.3.9 Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1 Monitors Providing Alarm and NOTE: Actions for INOPERABLE monitors are documented Automatic Termination in the Operations & Rad Effluent Shift Logs.4.3.3.9.1.a Liquid Waste Process Effluent Form 1/2-ADM-0606.F02: Channel Check Monitor Form 1/2-ENV-05.04.FO1: Source Check (2SGC-RQ100) 2MSP-43.39-1: Channel Calibration 1/20M-17.4A.C: Source Check 20M-25.4.L: Source Check 20M-25.4.N: Source Check_2OST-43.03: [CTS] Channel Functional Test [ITS] COT 4.3.3.9.2 Flow Rate Measurement Devices NOTE: Actions for INOPERABLE monitors are documented in the Operations & Rad Effluent Shift Logs and 112-ENV-05.04 4.3.3.9.2.a Liquid Radwaste Effluent 2MSP-25.01-1: 2SGC-P26A,B Ch Cal & [CTS] Ch Functional (2SGC-FIS100) Test [ITS] COT 2MSP-43.39-1: Channel Calibration __ Form 1/2-ADM-0606.F02: Channel Check 4.3.3.9.2.b Cooling Tower Blowdown Line 2MSP-31.04-1: Channel Calibration (2CWS-FT101) 2MSP-31.05-1: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check Beaver Valley Power Station 1 ProcedureNumber: ]Title: Unit: I Level Of Use: 1/2 I General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: 1 Page Number: 5 AA i 4nf"7.i a -ATTACHMENT C Page 5 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS EFFLUENT MONITOR SURVEILLANCES TABLE F: 3a 1/2-ODC-3.03, Attachment F Control 3.3.3.10: Maintain Gaseous Effluent Monitors in Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR DESCRIPTION PROCEDURE 4.3.3.10 Test Monitors at Table 4.3-13-Frequency 4.3.3.10.1 Gaseous Waste I Process Vent NOTE: Actions for INOPERABLE monitors are documented System in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05 4.3.3.10.1.a Noble Gas Activity Monitor IMSP-43.22-h: Channel Calibration Pri: (RM-1GW-108B) 1OM-19.4.E, H: Channel Check (Batch Release)Alt: (RM-1GW-109 Ch 5): for 1OM-19.4.E, H: Source Check continuous releases only, not 1/2-OM-19.4A.D: Source Check an alternate for batch releases 1/2-OM-19.4A.D: Channel Check (Batch Release)1 OST-43.09: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F01: Channel Check 4.3.3.10.1.b Particulate & Iodine Sampler Form 1/2-ADM-0606.FO1: Channel Check Pri: Filter Paper and Charcoal Cartridge for (RM-1GW-1 09)Alt: Filter Paper and Charcoal Cartridge for (RM-1GW-1 10)4.3.3.10.1.c System Effluent Flow Rate 1MSP-19.05-1: [CTS] Channel Functional Test [ITS] COT Measuring Device 1MSP-19.06-1: Channel Calibration Pri: (FR-1GW-108) Form 1/2-ADM-0606.FOI: Channel Check Alt: (RM-1GW-109 Ch 10) ....4.3.3.10.1 .d Sampler Flow Rate Measuring 1MSP-43.21-1: Channel Calibration Device Form 1/2-ENV-01.04.FO1: [CTS] Channel Functional Test Pri: (RM-1GW-109 Ch 15) [ITS] COT Alt: (Rotometer: FM-1GW-101 and Form 1/2-ADM-0606.FO1: Channel Check Vacuum Gauge: PI-1GW-1 35 for RM-1 GW-1 10).4.3.3.10.2 Auxiliary Building Ventilation NOTE: Actions for INOPERABLE monitors are documented System (Ventilation Vent) in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05 4.3.3.10.2.a Noble Gas Activity Monitor 1MSP-43.13-1: Channel Calibration Pri: (RM-1VS-101B) 1OST-43.07A: RM-1VS-109 [CTS] Channel Functional Test Alt: (RM-1VS-109 Ch 5) [ITS] COT 1OST-43.09: [CTS] Channel Functional Test [ITS] COT 1 OST-43.09A: Source Check Form 1/2-ADM-0606.FO1: Channel Check 4.3.3.10.2.b Particulate & Iodine Sampler Form 1/2-ADM-0606.FO1: Channel Check Pri: Filter Paper and Charcoal Cartridge for (RM-1VS-109) Alt: Filter Paper and Charcoal Cartridge for (RM-1VS-111) 4.3.3.10.2.c System Effluent Flow Rate 1MSP-44.07-1: [CTS] Channel Functional Test [ITS] COT Measuring Device 1MSP-44.08-1: Channel Calibration Pri: (FR-1VS-101) Form 1/2-ADM-0606.FO1: Channel Check Alt: (RM-1VS-109 Ch 10) -_I Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 65 of 79 ATTACHMENT C Page 6 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3a 1/2-ODC-3.03, Attachment F Control 3.3.3.10: Maintain Gaseous Effluent Monitors in Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR DESCRIPTION PROCEDURE 4.3.3.10.2.d Sampler Flow Rate Measuring 1MSP-44.07-1: Channel Functional Test-Device IMSP-44.08-1: Channel Calibration Pri: (RM-1VS-109 Ch 15) Form 1/2-ENV-01.04.FO1: [CTS] Channel Functional Test Alt: (Rotometer: FMA1VS-102 and [ITS] COT Vacuum Gauge: PI-1VS-659 Form 1/2-ADM-0606.FO1: Channel Check for RM-1VS-111) 4.3.3.10.3 Rx Containment / SLCRS NOTE: Actions for INOPERABLE monitors are documented (Elevated Release) in the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.31a Noble Gas Activity Monitor lMSP-43.20-h: Channel Calibration Pri: (RM-IVS-107B) 1OM-54.3 L5 Log: RM-1VS-107B Channel Check Alt: (RM-1VS-110 Ch 5) 1OST-43.07A: RM-1VS-110 [CTS] Channel Functional Test[ITS] COT IOST-43.09: [CTS] Channel Functional Test [ITS] COT 1 OST-43.09A: Source Check Form 1/2-ADM-0606.FO1: Channel Check 4.3.3.10.3.b Particulate & Iodine Sampler Form 1/2-ADM-0606.FO1: Channel Check Pri: FilterPaper and Charcoal Cartridge for (RM-1VS-110) Alt: Filter Paper and Charcoal Cartridge for (RM-1VS-112) 4.3.3.10.3.c System Effluent Flow Rate lMSP-44.09-1: Channel Calibration Measuring Device 1MSP-44.10-1: [CTS] Channel Functional Test [ITS] COT Pri: (FR-1 VS-112) Form l(2-ADM-0606.FO1: Channel Check Alt: (RM-1VS-110 Ch 10)4.3.3.10.3.d Sampler Flow Rate Measuring IMSP-43.19-h: Channel Calibration Device Form 1/2-ENV-01.04.FO1: [CTS] Channel Functional Test Pri: (RM-lVS-110 Ch 15) [ITS] COT Alt: (Rotometer: FM-IVS-103 and Form 1/2-ADM-0606.F01: Channel Check Vacuum Gauge: PI-1VS-660 for RM-1VS-1 12) Beaver Valley Power Station .Procedure Number: Title: ODCM: Index, Matrix and History of ODCM Changes Unit: Level Of Use: 1/2 General Skill Reference, Revision: Page Number: 5 ~ AA nf A7 ATTACHMENT C Page 7 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3b 1/2-ODC-3.03, Attachment F Control 3.3.3.10: Maintain Gaseous Effluent Monitors in Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR DESCRIPTION PROCEDURE 4.3.3.10 -Test Monitors at Table 4.3-13___________Frequency 4.3.3.10.1 SLCRS Unfiltered Pathway NOTE; Actions for:INOPERABLE monitors are documented (Ventilation Vent) in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05.4.3.3.10.1.a Noble Gas Activity Monitor 2MSP-43.36-1: Channel Calibration Pri: '(2HVS-RQ101B) 20ST-43.09: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check 2-ENV-05-21: Source Check (DRMS Auto Function)4.3.3.10.1.b Particulate & Iodine Sampler Form 1/2-ADM-0606.F02: Channel Check Pri: Filter Paperand Charcoal Cartridge for (2HVS-RQ 101A)4.3.3.10.1.c Process Flow Rate Monitor 2MSP-43.36-1: Channel Calibration Pri: (Monitor Item 29 for 2HVS- 2MSP-43.36A-I: [CTS] Channel Functional Test [ITS] COT VP101) Work Request: Channel Calibration (Velocity Probe)Form 1/2-ADM-0606.F02: Channel Check 4.3.3.10.1.d Sampler Flow Rate Monitor 2MSP-43.36-1: Channel Calibration Pri: (2HVS-FIT101-1) 2MSP-43.36A-l: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check 4.3.3.10.2 SLCRS Filtered Pathway NOTE: Actions for INOPERABLE monitors are documented (Elevated Release) in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05 .I 4.3.3.10.2.a Noble Gas Activity Monitor 2MSP-43.32-1: 2HVS-RQ109A Channel Calibration Pri: (2HVS-RQ109B) 2MSP-43.33-I: 2HVS-RQ109B,C,D Channel Calibration 2OST-43.08: (CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check 2-ENV-05-21: Source Check (DRMS Auto Function)4.3.3.10.2.b Particulate & Iodine Sampler 1/2-ADM-1611.F04: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2HVS-RQ109A) 4.3.3.10.2.c Process Flow Rate Monitor 2MSP-43.32A-I: (CTS] Channel Functional Test [ITS] COT Pri: (Monitor Item 29 for 2HVS- 2MSP-43.33-1: 2HVS-RQ109B,C,D, Channel Calibration FR22) Form 1/2-ADM-0606.F02: Channel Check l t Alt: (2HVS-FI22A and FI22C)2nd Alt: (2HVS-FI22B and FI22D)4.3.3.10.2.d Sampler Flow Rate Monitor 2MSP-43.32-1: 2HVS-RQ109A Channel Calibration Pri: (Monitor Items 28 & 72 for 2MSP-43.32A-l: [CTS] Channel Functional Test [ITS] COT 2HVS-DAU109A) 2MSP-43.33-1: 2HVS-RQ109B,C,D, Channel Calibration Form 1/2-ADM-0606.F02: Channel Check Procedure Number:.Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: "1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: I 5 67 of 78 ATTACHMENT C Page 8 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3b 1/2-ODC-3.03, Attachment F Control 3.3.3.10: Maintain Gaseous Effluent Monitors in Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR DESCRIPTION PROCEDURE 4.3.3.10.3 Decontamination Building NOTE: Actions for INOPERABLE monitors are documented Vent in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05 4.3.3.10.3.a Noble Gas Activity Monitor 2MSP-43.35-1: Channel Calibration Pri: (2RMQ-RQ301 B) 2OST-43.09: (CTS] Channel Functional Test [ITS] COT 2-ENV-05-21: Source Check (DRMS Auto Function)Form 1/2-ADM-0606.F02: Channel Check 4.3.3.10.3.b Particulate & Iodine Sampler Form 1/2-ADM-0606.F02: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2RMQ-RQ301A) 4.3.3.10.3.d Sampler Flow Rate Monitor 2MSP-43.35-1: Channel Calibration Pri: (2RMQ-FIT301-1) 2MSP-43.35A-1: [CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check 4.3.3.10.4 Condensate Polishing NOTE: Actions for INOPERABLE monitors are documented Building Vent in the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.4.a Noble Gas Activity Monitor 2MSP-43.38-1: Channel Calibration Pri: (2HVL-RQI1 12B) 2OST 2.43.09: (CTS] Channel Functional Test [ITS] COT Form 1/2-ADM-0606.F02: Channel Check 2-ENV-05-21: Source Check (DRMS Auto Function)4.3.3.10.4.b Particulate & Iodine Sampler Form 1/2-ADM-0606.F02: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2HVL-RQ1 12A)4.3.3.10.4.d Sampler Flow Rate Monitor 2MSP-43.38-1: Channel Calibration Pri: (2HVL-FIT1 12-1) 2MSP-43.38A-1: [CTS] Channel Functional Test (ITS] COT Form 1/2-ADM-0606.F02: Channel Check 4.3.3.10.5 Waste Gas Storage Vault Vent NOTE: Actions for INOPERABLE monitors are documented in the Operations & Rad Effluent Shift Logs and 112-ENV-05.05 4.3.3.10.5,a Noble Gas Activity Monitor 2MSP-43.37-1: Channel Calibration Pri: (2RMQ-RQ303B) 20ST-43,09: [CTS] Channel Functional Test (ITS] COT Form 1/2-ADM-0606.F02: Channel Check 2-ENV-05-21: Source Check (DRMS Auto Function)4.3.3.10.5.b Particulate & Iodine Sampler 1/2-ADM-1611.F04 Channel Check Pri: Filter Paper and Charcoal Cartridge for (2RMQ-RQ303A) 4.3.3.10.5.d Sampler Flow Rate Monitor 2MSP-43.37-1: Channel Calibration Pri: (2RMQ-FIT303-1) 2MSP-43.37A-l (CTS] Channel Functional Test (ITS] COT I Form 1/2-ADM-0606.F02: Channel Check Beaver Valley Power Station Procedure Number: 2-ODC-.0 Title: Unit: Level Of Use:--1/2 General Skill Reference 0 ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: " 6R nf7R ATTACHMENT C Page 9 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT CONCENTRATION SURVEILLANCES TABLE F: 4 1/2-ODC-3.03, Attachment G Control 3.11.1 .1: Maintain Effluent Concentration within 10 Times 10CFR20 EC's APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.1.1. 1.A Batch Waste Release Tanks: CHM CP 3: Sampling and Testing_Sample and Analyze Radioactive CHM CP 5: Radiochemical. Procedures Liquid Wastes per Table 4.11-1 CHM CP 8: Logs and Forms (Analysis)* CHM OP 9: Conduct of Operation Form 1/2-ADM-0606.F01 & F02: LW Tank Sampling Form 1/2-ENV-05.01.F01: LW Tank Sampling Form 1/2-ENV-05.1 1.F02: Rad Monitor Sampling 1/2-ENV-05.26: Sample Analysis Matrix 4.11.1.1.1.B Continuous Releases: CHM CP 3: Sampling and Testing Sample and Analyze Radioactive CHM CP 5: RadiochemicalProcedures Liquid Wastes per Table 4.11-1 CHM CP 8: Logs and Forms (Analysis) CHM CP 9: Conduct of Operation Form 1/2-ADM-0606.FO1 & F02: LW.Tank Sampling Form 1/2-ENV-05.01.F01: LW Tank Sampling Form 1/2-ENV-05.1 1.F02: Rad Monitor Sampling 1/2-ENV-05.26: Sample Analysis Matrix 4.11.1.1.2 Use ODCM Methodology to Form 1/2-ENV-05.04.F01: RWDA-L Assure Compliance 1/20M-17.4A.D: RWDA-L 4.11.1.1.3 Take Turbine Building Grab CHM CP 3: Sampling and Testing Sample When BV-1 Primary to CHM CP 5: Leak Rate Calculations Secondary Leakage Exceeds 0.1 CHM CP 8: Logs and Forms (Analysis) gpm (142 gpd) Form 1/2-ADM-0606.F01 & F02: Sump Sampling Form 1/2-ENV-05.01.F01: LW Tank Sampling Form 1/2-ENV-05.04.FO1: RWDA-L Form 1/2-ENV-05.1 1.F02: Rad Monitor Sampling 1/2-ENV-05.26: Sample Analysis Matrix 4.11.1.1.4 Obtain Turbine Building Grab CHM CP 3: Sampling and Testing Sample When BV-2 Primary to CHM CP 5: Leak Rate Calculations Secondary Leakage Exceeds 0.1, CHM CP 8: Logs and Forms (Analysis) gpm (142 gpd) Form 1/2-ADM-0606.FO1 & F02: Sump Sampling Form 1/2-ENV-05.01.F01: LW Tank Sampling Form 1/2-ENV-05.04.F01: RWDA-L Form 1/2-ENV-05.1
- 1. F02: Rad Monitor Sampling 1/2-ENV-05.26:
Sample Analysis Matrix 4.11.1.1.5 Obtain Grab Samples Prior to BV- Form 1/2-ADM-0606.FO1 & F02: Sump Sampling 2 Recirculation Drain Pump Form 1/2-ENV-05.01.F01: LW Tank Sampling Discharge to Catch Basin No. 16 20M-9.2: Rx Plant Vents and Drains (CB-16)20M-9.4F: Drain RSS Pump Casing / Pit 20M 51: OM Clearance 51-86'(2DAS-P215A/B) 1/2-ENV-05.26: Sample Analysis Matrix Beaver Valley Power Station [ProcedureNmorC101 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 5 69 of 79 ATTACHMENT C Page 10 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT DOSE SURVEILLANCES TABLE F: 5 1/2-ODC-3.03, Attachment H Control 3.11.1.2: Liquid Effluent Dose APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.1.2.1 Using the ODCM -Determine Form 1/2-ENV-05.04.FO1: RWDA-L'Effmulative Dose From Liquid SAP Order (issue NPD3NRE Letter: Monthly Dose Projection) Effluents Every 31 Days 1/2OM-17.4A.D: RWDA-L Beaver Valley Power Station OProcedureNumber Title: Unit: Level Of Use: 1/2 L General Skill Reference ,`ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: I ATTACHMENT C Page 11 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-I AND 2 LIQUID EFFLUENT TREATMENT SURVEILLANCES TABLE F: 6 1/2-ODC-3.03, Attachment I Control 3.11.1.3: Liquid Effluent Treatment System APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.1.3.1 Using the ODCM -Project the Liquid Form 1/2-ENV-05.04.FO1: RWDA-L Release Dose Every 31 Days SAP Order (IssueNPD3NRE Letter: Monthly Dose Projection) ~1/20M-17.4A.D: RWDA-L 0 B Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use:*1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 1 5 71 of 79 ATTACHMENT C Page 12 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F: 7 1/2-ODC-3.03, Attachment J Control 3.11.1.4: Maintain Liquid Tank Activity within the following limits:<21 Curies in 1BR-TK-6A<21 Curies in 1BR-TK-6B_<7 Curies in 1 LW-TK-7A<7 Curies in 1 LWVTK-7B_<5 Curies in 1QS-TK-1<139 Curies in 2QSS-TK21<10 Curies in Unit 1 and Unit 2 miscellaneous temporary outside -radioactive liquid storage tanks.APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.11.1.4.1 Every 7 days Analyze a tank sample Form 1/2-ENV-05.01.F03: Activity Determination when radioactive material is added to Form 1/2-ENV-05.04,FO1: RWDA-L tanks except the RWST's. 1/2-ENV-05.26: Sample Analysis Matrix 1OM-8.4.Z: Recirculate Test Tanks Thru Ion Exchanger For RWST's, analyze sample within 1OM-17.4.AJ: LW Transfer to 1LW-TK-7A&B 7 days of reactor cavity drain down 1OM-54.3 L5 Log Item 197: back to the RWST. 1OM-54.3 L5 Log Item 132: 1OM-54.3 L5 Log Item 134: IOM-54.3 L5 Log Item 200: 20M-17.4B: LW to SG Blowdown Tank BPProcedure Number.Beaver Valley Power Station-I " 1i2-ODC-1.01 Title: Unit: Level Of Use: 1/2, General Skill Reference. ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number: 5 I 72of 7R ATTACHMENT C Page 13 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND2 GASEOUS EFFLUENT DOSE SURVEILLANCES TABLE F: 8 1/2-ODC-3.03, Attachment K Control 3.11.2.1: Gaseous Effluent Dose Rates APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.2.1.1 Using the ODCM -Determine the Form 1/2-ENV-05.05.F01: RWDA-G Noble Gas Effluent Dose Rate Form 1/2-ENV-01.03.FO1: Continuous Release Permit Form 1/2-ENV-05.06.FO1: Abnormal Gaseous Releases 1OM-19.4E, H: RWDA-G for Unit 1 GWDT's 1/2OM-19.4A.B: RWDA-G for Unit 2 GWST's , 4.11.2.1.2 Sample and Analyze per Table 4.11-2 to Determine Inhalation Pathway Dose 4.11.2.1.2.A Waste Gas Storage Tank -CHM CP 3: Sampling and Testing Grag Sample Each Tank CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis) CHM CP 9: Conduct of Operation Form 1/2-ADM-0606.FO1 & F02: GW Tank Sampling Form 1/2-ENV-05.02.FO1: GW Tank Sampling Form 1/2-ENV-05.05.FO1: RWDA-G Form 1/2-ENV-05.1 1.F01: Rad Monitor Sampling 1/2-ENV-05.26: Sample Analysis Matrix 4.11.2.1.2.B Containment Purge -CHM CP 3: Sampling and Testing Grag Sample Each Purge CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis) CHM CP 9: Conduct of Operation Form 1/2-ADM-0606.F01 & F02: GW Tank Sampling Form 1/2-ENV-05.05.FO1: RWDA-G Form 1/2-HPP-3.07.003.F01: Air Sample Record Form 1/2-ENV-05.11.F01: Rad Monitor Sampling 1/2-ENV-05.26: Sample Analysis Matrix 4.11.2.1.2.C Ventilation Systems 4.11.2.1.2.C.1 BV-1 Grab and Continuous CHM CP 3: Sampling and Testing thru Samples CHM CP 5: Radiochemical Procedures 4.11.2.1 .C.3 CHM CP 8: Logs and Forms (Analysis) and CHM CP 9: Conduct of Operation 4.11.2.1.2.D.1 Form 112-ADM-0606.FOI & F02: GW Tank Sampling thru Form 112-ENV-01.03.FO1: Continuous Release Permit 4.11.2.1.2.D.3 Form 1/2-ENV-05.1 1 .F01: Rad Monitor Sampling Form 1/2-ENV-05.25..Fxx: RMS & DRMS Valve Verification 1 -HPP-5.01.001: SA-9/1 0 Emergency Operation 1-HPP-5.01.002: SPING-4 Emergency Operation 1/2-ENV-05.26: Sample Analysis Matrix 4.11.2.1.2.C.4 BV-2 Grab and Continuous CHM CP 3: Sampling and Testing thru Samples CHM CP 5: Radiochemical Procedures 4.11.2.1.2.C.8 CHM CP 8: Logs and Forms (Analysis) and CHM CP 9: Conduct of Operation 4.11.2.1.2.D.4 Form 1/2-ADM-0606.F01 & F02: GW Tank Sampling thru Form 1/2-ENV-01.03.F01: Continuous Release Permit 4.11.2.1.2.D.8 Form 1/2-ENV-05.11 .F01: Rad Monitor Sampling Form 112-ENV-05.25..Fxx: RMS & DRMS Valve Verification 2-HPP-5.04.001: Emergency Operation of WRGM Assembly l/2-ENV-05.26: Sample Analysis Matrix I B Procedure Number: Beaver Valley Power Station 1/2-ODC-1.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: Page Number:.5 7-3 of 78 ATTACHMENT C Page 14 of 19.ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT AIR DOSE SURVEILLANCES TABLE F: 9 1/2-ODC-3.03, Attachment L Control 3.11.2.2: Gaseous Effluent Air Doses APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.11.2.2.1 .Using the ODCM -Determine the Form 1/2-ENV-05.05.FO1: RWDA-G Noble Gas Cumulative Dose Form 1/2-ENV-01.03.FO1: Continuous Release Permit Contributions Every 31 Days Form 1/2-ENV-05.06.FO1: Abnormal Gaseous Releases Form 1/2-ENV-05.11 .FO1: Rad Monitor Sampling-__*_SAP Order (Issue NPD3NRE Letter: Monthly Dose Projection) Beaver Valley Power Station Procedure lNuI Title: Unit: Level Of Use: 1/2 General Skill Reference Revision: Page Number:.5 74 nf 7R 0 ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 15 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SURVEILLANCES TABLE F: 10 1/2-ODC-3.03, Attachment M Control 3.11.2.3: Gaseous Effluent Particulate And Iodine Doses, APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SRR __4.11.2.3.1 Using the ODCM -Determine the Form 1/2-ENV-05.05.FO1: RWDA-G Particulate & Radioiodine Cumulative Form 1/2-ENV-01.03.FO1: Continuous Release Permit Dose Contributions Every 31 Days Form 1/2-ENV-05.06.F01: Abnormal Gaseous Releases Form 1/2-ENV-05.11.F01: Rad Monitor Sampling SAP Order (Issue NPD3NRE Letter: Monthly Dose Projection) Beaver Valley Power Station Procedure Number: 1/2-ODC-1.01 Title: Unit: Level Of Use: p 1/2 I General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
- Page Number:-5 I 75 of 79 ATTACHMENT C Page 16 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-I AND 2 GASEOUS EFFLUENT TREATMENT SURVEILLANCES TABLE F: 11 112-ODC-3.03, Attachment N Control 3.11.2.4:
Gaseous Effluent Treatment System APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.11.2.4.1 Using the ODCM -Project the Gas Form 1/2-ENV-05.05.FO1: RWDA-G Release Dose from the Site Every 31 Form 1/2-ENV-01.03.FO1: Continuous Release Permit Days Form 1/2-ENV-05.06.F01: Abnormal Gaseous Releases SAP Work Order (Issue SHP Letter for Monthly Dose Projection) Beaver Valley Power Station Procedure Numer:ODC-10 I I Title:.Unit: 1/2 Level Of Use: General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision: 1 Page Number: 7A nf 7R ATTACHMENT C Page 17 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F: 12a 1/2-ODC-3.03, Attachment 0 Control 3.11.2.5: Maintain Gas Storage Tank Activity within the following limits: 1GW-TK-1A: <52000 Curies Noble Gas (Considered Xe-133)1 GW-TK-1 B: <52000 Curies Noble Gas (Considered Xe-1 33)1GW-TK-1B: <52000 Curies Noble Gas (Considered Xe-133)APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.11.2.5.1 Determine Tank Gas Contents when Form 1/2-ENV-05.02.FO1: GW Tank Sampling Adding Rad Material & (RCS Activity 1OM-19.4.G: GW Disposal System>10ouCi/ml) 1/2-ENV-05.26: Sample Analysis Matrix:1 BV-2 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F: 12b 1/2-ODC-3.03, Attachment 0 Control 3.11.2.5: Maintain Gas Storage Tank Activity with the following limit: 2GWS-TK25A thru 25G: <19000 Curies Noble Gas (Considered Xe-1 33) in any connected group of Gas Storage Tanks APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.2.5.1 Determine Gaseous Waste Tank Form 1/2-ENV-05.02.FO1: GW Tank Sampling Rad Material When Adding Rad 20M-19.2: GW Precautions & Limitations Material to the Tank. 20M-19.4G: GW transfer from Unit 2 2-M-54.3 L5 Log Item 133 1/2-ENV-05,26: Sample Analysis Matrix I Procedure Number: Beaver Valley Power Station 1/2-ODC-1.O1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Index, Matrix and'History of ODCM Changes Revision: Page Number: 77 of 78 ATTACHMENT C Page 18 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 TOTAL DOSE SURVEILLANCES TABLE F: 13 1/2-ODC-3.03. Attachment P Control 3.11.4.1: Liquid And Gaseous Doses APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.11.4.1.1 LMing the ODCM- Determine Form 1/2-ENV-01.05.F01: Annual RETS Report (40CFR190) Cumulative Gas & Liquid Dose per Form 1/2-ENV-05.04.FO1: RWDA-L Control 3.11.1.2, 3.11.2.2, 3.11.2.3 Form 1/2-ENV-05.05.FO1: RWDA-G Form 1/2-ENV-01.03.FO1: Continuous Release Permit Form 1/2-ENV-05.06.FO1: Abnormal Gaseous Releases 1/2-ENV-01.04: Effluent Data Logs (40CFR190) Beaver Valley Power Station e / dureNumb rDC: 01 Title: Unit: Level Of.Use: 1/2 General Skill Reference Revision: Page Number: 5 1 7Ri of 7RI "" ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 19 of 19 ODCM CONTROLS PROCEDURE MATRIX I BV-1 AND 2 REMP PROGRAM SURVEILLANCES TABLE F: 14 1/2-ODC-3.03, Attachment Q Control 3.12.1: Radiological Environmental Monitoring Program (REMP)APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.12.1.1 Using Locations in the ODCM -Collect 1/2-ENV-02.01: Description of overall REMP and Analyze Samples per Tables 1/2-ENV-03.01: Environmental Sampling 3.12-1, 3.12-2 & 4.12-1d TABLE F: 15 1/2-ODC-3.03, Attachment R Control 3.12.2: Land Use Census APPLICABILITY: At All Times TABLE F: 16 1/2-ODC-3.03, Attachment S Control 3.12.3: Interlaboratory Comparison Program APPLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.12.3.1 Include Analysis Results of the 1/2-ENV-02.01: Description of overall REMP Interlaboratory Comparison Program in the Annual Radiological Environmental Report I 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 4 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 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 5 2 of 41 TABLE OF CONTENTS 1.0 P U R P O SE ........................................................................................................................................ 3 2.0 SC O P E ............................................. ...... ................................................. ................... ................... 3
3.0 REFERENCES
AND COMMITMENTS ................ ........................................................ ........... 3 3 .1 R eferences .............................................................................................................................. 3 3.2 C om m itm ents ......................................................................................................................... 6 4.0 RECORDS AND FORMS ....................................................................................................... 6 4 .1 R eco rd s ................................................................................................................................... 6 4 .2 F orm s ...................................................................................................................................... 6 5.0 PRECAUTIONS AND LIMITATIONS ....................................................................................... 6 6.0 ACCEPTANCE CRITERIA .......................................................................................................... 7 7.0 P R E R E Q U ISIT E S ............................................................................................................................ 7 8.0 P R O C E D U RE .................................................................................................................................. 8 8.1 A larm Setpoints ...................................................................................................................... 8 8.1.1 BV-1 Monitor Alarm Setpoint Determination ................................................. 8 8.1.2 BV-2 Monitor Alarm Setpoint Determination ............................................... 13 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) ...................................... 25 8.4 Liquid Radwaste System .................................................................................................. 25 8.4.1 BV-1 Liquid Radwaste System Components .................................................. 26 8.4.2 BV-1 Laundry and Contaminated Shower Drain System Components ...... 27 8.4.3 BV-2 Liquid Radwaste System Components ...................................................... 27 ATTACHMENT A LIQUID SOURCE TERMS ........................................................................... 29 ATTACHMENT B RECIRCULATION TIMES ............................................................................. 33 ATTACHMENT C INGESTION DOSE COMMITMENT FACTORS:..................................... 35 ATTACHMENT D LIQUID RADWASTE SYSTEM .................................................................... 38 ATTACHMENT E SITE BOUNDARY FOR LIQUID EFFLUENTS .......................................... 41 Procedure Number: Beaver Valley Power Station o /2-ODC-2.0m Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1_5 a of 41 1.0 PURPOSE 1.1 This procedure provides the calculational methodology to be used for determination of the following release parameters as denoted in ICTS] the Administrative Controls Section of the Unit 1/2 Technical Specifications [ITS] T.S. 5.5.2.(32"1)
1.1.1 Liquid
effluent monitor alarm setpoints ([CTSJ Technical Specification 6.8.6.a, Item I[ITS] T.S. 5.5.2.a)1.1.2 Liquid effluent release concentration calculations (ICTS] Technical Specification 6.9.6.a, Item 2 [ITS] T.S. 5.5.2.b)1.1.3 Liquid effluent dose projection and cumulative dose calculations ([CTS] Technical Specification 6.8.6.a, Items 4 and 5[ITS] T.S. 5.5.2.d and T.S. 5.5.2.e)1.2 This procedure also provides information related to the following:
1.2.1 Liquid
Radwaste Treatment System ([CTSJ Technical Specification 6.8.6.a, Item 6 IITSl T.S. 5.5.2.f)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-I 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 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_5 4 of 41 S 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)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-RQIO0 3.1.2.4.1 The Isotopic Efficiencies for 2SGC-RQ 100 are superceded 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 superceded 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-00 17; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR's, 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 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: 5 -5 of 41 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 1 OCFR 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 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 1/2-ADM- 1640, Control of the Offsite Dose Calculation Manual 3.1.3.10 1/2-ADM-0 100, Procedure Writers Guide 311.3.11 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 1.1-1a 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 [1 LW-TK-7A/7B]. CA-02, Revise ODCM Procedure 1/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit I 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 1 A-302) to License No.DPR-66. This amendment to the Unit 1 license was approved by the NRC on July 19, 2006.3.1.3.18 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. Procedure Number: Beaver Valley Power Station 1.rou 1u-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference_, ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 6of 41 " 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-IRW-100] and [RM- IDA- 100] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275.3.1.3.21 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-RQ 101 ] for incorporation of the Extended Power Update at Unit 2 (ECP-04-0441) per Unit 2 TS Amendment No. 156.3.2 Commitments 3.2.1 [CTS] Unit 1/2 Technical Specification 6.8.6.a[ITS] T.S. 5.5.2 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 P(31.3.1) 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-*I monitors, Alert and High terminology is used for BV-2 monitors. 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: Page Number: 1_5 7_of 41 5.2.2 BV-2 setpoints are presented in uCi/ml 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-I and 2 Offsite Dose Calculation Manual.5.3.1 Ifi 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 E Figure 5-1.5.4 This procedure includes Improved Technical Specifications ([ITS]) information that is NOT applicable to current Technical Specifications ([CTSI) and [CTSJ information that is NOT applicable in [ITS]. The [CTSJ information shall be used prior to the [ITS] effective date.The [ITS] information shall be used on or after the [ITS] effective date.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 50.3 6a, 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)6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3. 3.1°)and 1/2-ADM-1640.(3.1.3.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001 3-'3-11 and l/2-ADM-1640. (3.3 9 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and format. I Procedure Number: Beaver Valley Power Station "1/2-ODC-2.01 Title: Unit: Level Of Use: I 1/2 General Skill Reference .ODCM: LIQUID EFFLUENTS Revision: Page Number: ..'i.I_ _ _ _ _ _ _ _1_ _5__ _ _8__of__4 S 8.4 8.0 PROCEDURE Alarm Setpoints 8.1.1 BV-I Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's 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 excieds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases. (31.15)The methodology described in Section 8.1.1.2 is an alternative method to be used to determine the (RM- 1 LW- 104 or RM- 1 LW- 116) monitor HIGH-HIGH Alarm Setpoint (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/mland 7.33E-3 uCi/ml. This concentration is equivalent to the respective HHSP's derived in Section 8.1.1.1 and allows for respective tritium concentrations up to 4.26E+0 uCi/ml and 9.94E+0 uCi/ml.(3'"'5)8.1.1.1 BV-i SetDoint Determination Based On A Conservative Mix.1 The Alarm Setpoints for the liquid monitors 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-lLW-104 3.53E+5 < 3.53E+5 < 2.47E+5 Laundry And Contaminated RM- ILW- 116 8.24E+5 < 8.24E+5 < 5.77E+5 Shower Drains Monitor Component Cooling/ RM-IRW-100 2.57E+4 < 2.09E+4 < 1.46E+4 Recirculation Spray Hx River 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 1.22E+4 < 1.20E+4 < 8.43E+3 Monitor The setpoints for RM-ILW-104 and RM-ILW- 116 are based on the following conditions. The setpoint bases for all monitors can be found in Calculation Package ERS-ATL-93-021 and/or S&W Calculation Package No. 8700-UR(B)-223.(3
- 18) ?
Beaver Valley Power Station Proedure 7ODC-2 O Title: Unit: Level Of Use: 1/2 IGeneral Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 9_of 41 0 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 021(3 .1.5, 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 35 gpm for the Liquid Waste Effluent Monitor (RM- 1 LW- 104).* Discharge flow rate prior to dilution of 15 gpm for the Laundry and Contaminated Shower Drains Monitor (RM- 1 LW- 116).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: HHSp=542F [1.1(l)-i] f where: HHSP = Monitor HIGH-HIGH Alarm Setpoint above background (ncpm).542 = Most restrictive proportionality constant based on nominal flow conditions: 542 3.53E+5 ncpm x 35 gpm ÷22,800 gpm (RM-ILW-104) 542 8.24E+5 ncpm x 15 gpm + 22,800 gpm (RM-ILW-1 16)F Dilution water flow rate (gpm), BV-I 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- I 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- a. Beaver Valley Power Station Procedure Nuer.-ODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: , 1_5 -10_of41 S 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: SiAi [1.1(1)-2= ZAi i where: Ai = Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1. 1- la.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: 8.1.1.1.2 Ct= F fE Si i OECi[1.1(1)-3] r.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-1LW-104). = 15 gpm for Laundry and Contaminated Shower Drains Monitor (RM-ILW-116).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 new 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 (1)-2]. Beaver Valley Power Station Procedure Nuber: Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 11 of 41 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] 8.1.1.1.4 BV- I Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the-radionuclides; (CR) was determined by: CR= z Ci Ei [1.1(1)-5] i where: Ei= 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. (31.1.4)8.1.1.1.5 BV- I Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint 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 HIGH-HIGH Alarm Setpoint based on this flow rate for the Liquid Waste Effluent Monitor (RM-1LW-104) and the Laundry and Contaminated Shower Drains Monitor (RM- ILW-l 16) 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. .Beaver Valley Power Station odur Nu :ODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference, ODCM: LIQUID EFFLUENTS Revision: ,-Page Number: 4 5 __12 of 41 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 [l.1(1)-6] 1.25 7 Ci 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 4 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-la. The OEC is set at 10 times the new 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(1)-7] i where: Ei =The detection efficiency of the monitor for radionuclide "i" (cpm/uCi/ml) from ATTACHMENT A Table 1.1-la. If not listed there, from Calculation"Package ERS-SFL-92-039.(
- 4) '4 1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.I I p Beaver Valley Power. Station Procedure Number: B1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision:
Page Number: 1 5 13 of 41 8.1.1.2.3 BV-1 Monitor HHSP The liquid effluent monitor HIGH-HIGH Alarm Setpoint 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] where: HSP= Monitor HIGH-HIGH Alarm Setpoint above background. CR = Calculated monitor count rate (ncpm) from equation [I. 1(1)-7].f = Maximum acceptable discharge flow rate prior to dilution determined by equation [ 1.1(1)-6]. = Actual maximum discharge flow rate to be maintained for the discharge. The reduced value of eJ 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 that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's 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 2 6)The methodology described in Section 8.1.2.2 is an alternative method to be used to determine the (2SGC-RQ100) monitor HIGH Alarm Setpoint (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 HIGH Alarm Setpoint 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 5.61 E-9 uCi/ml/cpm determined for the nuclide mix.(3.1.2.6) Beaver Valley Power Station Procedurembr Title: Unit: Level Of Use: 1/2 General Skill Reference, ODCM: LIQUID EFFLUENTS Revision:, : -Page Number:: 4 5 ., 14 of.41 8.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the liquid monitors shall be set at the values listed in the following Table: BV-2 LIQUID MONITOR SETPOINTS yCi/ml Above Background Monitor DV HSP ASP Liquid Waste Effluent 2SGC-RQ100 1.14E-3 < 1.14E-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 <54.30E-5 < 3.01E-5 The setpoint for 2SGC-RQ 100 is based on the following conditions, however, the setpoint bases for 2SWS-RQ10I and 2SWS-RQ 102 can be found in Calculation Package ERS-ATL-93-021 .(3.1.2.6)
- Source terms given in ATTACHMENT A Table 1.1-l b. These source terms (without Zn-65) have been generated by using models and input similar to NUREG- 4 0017. The inputs are given in 1/2-ODC-3.01.
The Zn-65 source term was generated via Calculation Package No. ERS-ATL-93-02 1.26, 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-RQ 100).* A software conversion factor of 5.6 1E-9 uCi/ml/cpm associated with Liquid Waste Effluent Monitor (2SGC-RQ 100).(' 1.2.6) Beaver Valley Power Station Proceur N ODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1 1 5 15 of 45 The above setpoint for (2SGC-RQ 100) 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 = Monitor HIGH Alarm Setpoint (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).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-l b.* 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: Si = Ai [1.1(2)-2] 1 Ai i where: Ai =Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1.1-l b. 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: 5 __16 of 41 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: C, F [1.1(2)-3] fX 1 i Si OECi where: F = Dilution water flow rate (gpm), BV- 1 plus BV-2 Cooling Tower Blowdown Rate (not including release out through the Emergency Outfall Structure). = 22,800 gpm = (15,000 gpm BV-I + 7,800 gpm BV-2).f = Maximum acceptable discharge flow rate prior to dilution (gpm).= 80 gpm for Liquid Waste Process Effluent Monitor (2SGC-RQ 100).OECi = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-lb. The OEC is set at 10 times the new 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 (2)-2].BV-2 Maximum Acceptable Concentration (Individual Radionuclide) The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide "1T in the liquid effluent prior to dilution (Ci) was determined by: Ci = Si Ct [1.1(2)-4] 8.1.2.1.3 Beaver Valley Power Station Procedure Number: P/2-ODC-2.01 Title: Unit: Level Of Use:..1/2 , General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1 5 17 of 4J 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)-5] where: 5.6 1E-9 = Conversion factor (uCi/ml/cpm), an average determined for the source term mix.Ei = Detection efficiency of the monitor for radionuclide "i'(cpm/uCi/ml) from ATTACHMENT A Table 1.1-l b. If not listed there, from Calculation Package ERS-SFL 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. Beaver Valley Power Station ProdureNurODC201 Title: Unit: Level Of Use.1J/2 IGeneral Skill Reference ODCM: LIQUID EFFLUENTS j Revision: Tpage Number: 5 !__18 of 45 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 C__L 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. C i 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 new 10 CFR 20, Appendix B (20.1001-20.2402) ATTACHMENT A Table 2, Col. 2"EC values. Beaver Valley Power Station Procdure NuO7 2 0 1 Title: Unit' Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 ' 19of 41 8.1.2.2.21 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) ZX C 1 E 1 [1.1(2)-7] where: Ei= 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 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.5.6 1E-9 Conversion factor (uCi/ml/cpm), an average determined for the source term mix.8.1.2.2.3 BV-2 Monitor HSP The liquid effluent monitor HIGH Alarm Setpoint 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 [1.1(2)-8] where: HSP = Monitor HIGH Alarm Setpoint 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].= Actual maximum discharge flow rate to be maintained for the discharge. The reduced value of fJ may be due to pump limitations or administrative selection. 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: "..... ..__5_. ... 20 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-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 through the mixing eductors. This will be accomplished by recirculating the tank contents for at least the time periods indicated in ATTACHMENT B Table 1.2-1a and 1.2-lb. BV-I 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, R [1.2-1]MDF 4 where: Conci = Concentration of radionuclide 'T' at the unrestricted area (uCi/ml).Ci= Concentration of radionuclide "'T 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 OEC's.Before a release is authorized, Equation [1.2-2] must be satisfied. Xi (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 tl.new 10 CFR 20, Appendix B, (20.1001-20.2402) Table 2, Col. 2 EC values.(3.1.13, 31.2.1) Procedure Number: Beaver Valley Power Station ro2-O DCm2e01 Title: Unit: Level Of Use: 1 1/2 I General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 21 of 41 8.2.1.2 Post-Release Following release from the batch tank, the Post Dose Correction Factor will be calculated in the following manner: PDCF = (VAt)/(DFA)(Vlt)/(DFI) [1.2-3]where: PCDF = Post Dose Correction Factor.VAt =DFA =VIt -Actual Volume of tank released (gal).Actual Dilution Flow during release (gpm).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 where:[1,2-4]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 Vtk Concentration of radionuclide "i" (uCi/ml) in batch release during time period k.= 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 1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Referencelj ODCM: LIQUID EFFLUENTS Revision: Page Number: .1 5 22 of 41 To show compliance with ODCM CONTROL 3.11.1.1, the following relationship must be satisfied: YZi(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 [ 1.2-1 ] with Cik, the concentration of isotope i in the continuous rerease. 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- I and 2 utilize the concept of a shared liquid radioactive waste system according to NUREG 0133.(3.13.
- 1) 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 Z Aix Z m Atk Cik Fk [1.3-1]i k=l where: D, = The cumulative dose comm itment to the total body or any organ, -r, from the liquid effluents for the total time period m E Atk (mrem)k=1 Atk = 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 Atk from any liquid release. Procedure Number: Beaver Valley Power Station. .1/2-ODC-2.m1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number:_ 5 23 of 41 Ai,= The site related ingestion dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter (mrem-ml per hr-uCi)from ATTACHMENT C Table 1.3-1.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-I 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(3.1.3.4) methodology and is a factor of 10 below the limit specified in NUREG-0133, Section 4.3.(3.31) The dose factor Ai, was calculated for an adult for each isotope using the following equation from NUREG-0133.(3131) Ai-r= 1.14E5 (730/Dw + 21BFi)DF 1.[1.3-21 where: 1.14E5 1E6pCi x lE3ml] F lyr I uCi 1 [8760 hr 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). Beaver Valley Power Station ProcedureNumrODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference.,- ODCM: LIQUID EFFLUENTS Revision: Page Number:....__5_ .of 41S.6 BFi Bioaccumulation factor for radionuclide 'i" in fish from Table A-I of Regulatory Guide 1.109(3135) (pCi/kg per pCi/l). However, if data was not available from that reference, it was obtained from Table 6 of UCRL-50564.(3.1.3.8) The bioaccumulation factor for niobium (300 pCi/kg per pCi/l) was not obtained from either of the above references noted. It was otained from IAEA Safety Series No. 57. Justification for use of this value is documented in Appendix A to Calculation Package No. ERS-ATL 027.(3.1.3.6) 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,'1".3.5) or NUREG-0 i72.(3.1.3.7) .A table of Ai, values for an adult at BV-I and BV-2 are presented in ATTACHMENT C 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 requried.(3'1'2)-4-b Beaver Valley PProcedure Number: Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use: A/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: ODCM: LIQUID EFFLUENTS 1 5 25 of 41 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 rnrem 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 acco'ding to the following equations: When including pre-release data, D 3 1 =AB 31-+ C [1.3-7]T When not including pre-release data, D31 -31+C [1.3-8]T where: D31= 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 Liqiuid 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 D Figures 1.4-1 and 1.4-2 respectively. A diagram showing the liquid effluent* release points is provided as ATTACHMENT D Figure 1.4-3. A diagram of the site boundary for liquid effluents is provided as ATTACHMENT E 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. Procedure Number:.BeaverValley Powrtaio_______e_'mer Beav2Power Station 12-ODC-2.01 Title: Unit: Level Of Use:_/2 General Skill Reference5..-, ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 I 26 of 41 *8.4.1 BV-1 Liquid Radwaste System Components 8.4.1.1 1LW-TK-2A/2B: High Level.Waste Drain Tanks There are two of these tanks, each tank has a capacity of 5,000 gallons. They are located on the northwest wall of the Auxiliary Building (elevation 735'). They receive liquid wastes from the vent and drain system.8.4.1.2 1LW-TK-3A/3B: Low Level Waste Drain Tanks-There are two of these tanks, each tank has a capacity of 2,000 gallons. They are located in the northwest corner of the Auxiliary Building (elevation 735'). They also receive liquid wastes from the vent and drain system. : 8.4.1.3 1LW-I-2: Liquid Waste Pre-Conditioning Filter & Demineralizer The main purpose of the pre-conditioning filter & demineralizer is to clean liquid waste water of particulate and dissolved radioactive contaminants that is stored in ILW-TK-2A/2B and 1LW-TK-3A/3B. There are four resin beds and a pre-conditioning filter associated with this system. The pre-conditioning filter can be customized with varying grades of activated charcoal intended for removal of radionuclides in a colloidal state. Each of the demineralizer beds can be customized with different resins for effective removal of chemical contaminants along with radioactive contaminants. Generally, beds 1 and 2 contain a Cation Resin and beds 3 and 4 contain a Mixed Bed Resin. This system is located in the Decontamination Building (elevation 735').8.4.1.3.1 An evaporator (6 gpm) was originally used to process liquid waste at Unit 1.However, this evaporator was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste. 8.4.1.4 1LW-TK-7A/7B: Steam Generator Drain Tanks There are two of these tanks, each tank has a capacity of 34,500 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 mustbe recirculated prior to sampling for discharge permit preparation. 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: 5 27 of 41 8.4.1.5 RM-1LW-104: Liquid Waste Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged. 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 capacity of 1200 gallons. They are located in the northwestcorner 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. 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 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. 2LWS-TK2IA/21B: Waste Drain Tanks There are two of these tanks, each tank has a capacity of 10,000 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 tank volumes must be recirculated prior to sampling for discharge permit preparation. Procedure Number: Power Station 1/2-ODC-2.01 Title: Unit: Level Of Use:* 1/2 General Skill Reference_ ODCM: LIQUID EFFLUENTS Revision: Page Number:.,______LIQUID._EFFLUENTS_ 5 28 of 41 0 8.4.3.2 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').8.4.3.2.1 Two evaporators (20 gpm each) were orignially used to process liquid waste at Unit 2. However, this evaporator was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste. 8.4.3.3 2SGC-TK23A/23B: Steam Generator Blowdown Test Tanks There are two of these tanks, each has a capacity of 18,000 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. 8.4.3.4 2SGC-TK21A/21B: Steam Generator Blowdown Hold Tanks There are two of these tanks, each has a capacity of 50,000 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 I 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. 8.4.3.5 2SGC-RQ1OO: Liquid Waste Effluent Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged. 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 - Procedre-Number:--Beaver Valley Power Station 1o2-ODC-2.m1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number:__5 29_of 41 ATTACHMENT A Page 1 of 4 LIQUID SOURCE TERMS TABLE 1.1-1a BV-1 LIQUID SOURCE TERM (4)MUE Or-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Z i-.65 (3.1,13)Np-239 Br-83 Br-84 Br-85 Rb-86 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-131m Te-131 1-131 Te-132 1-132 1-133 A, ANNUAL RELEASE (CI)13E-3 3.1F4 1.6E-3 83E4 1.4E-2 ZOE-3 269E-2 1.4E4.25E-5 2.5F5.2.SE-5 27E,6 7.56-5 2.9E-4 1.1 E-5 9.4E-6 8.7E-6 5.7E-5 7.4E-7 5.1 E-5 5.2E-5 1.3E-5 1.1E-2 1.1 E-2 3.4E-5 1.0E-5 3.4E-5 1.0E-5 2.5E-5 2.6E-4 2.7E-4 1.1 E-3 6.7E-4 1.2E-4 1.6E-4 3E-5 1.6E-1 4.3E-3 4.9E-3 4.OE-2 (3)OEC_5E-3 3E,4 1E-3 15.4 2F_,4 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 1 E-2 3E-4 3E-5 6E-2 (5)2E-4 9E-5 IE-3 7E-5 4E-3 2E-4 8E-5 8E-4 IE-5 9E-5 1 E-3 7E-5 Ei DEIECI'ON EFFICIENCY 1.18E+7 859E+7 (5)9.17E+7 1.16E+8 1.73E+8 4.67E+7 8.49E+7 136E-f6 9.75E+7 6.19E+6 (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 1.12E+7 3.08E+8 1 .82E+8 1.20E+8 1.11 E+8 1.17E+8 2.66E+8 9.90E+7 Procedure Number: Beaver Valley Power Station P u /2-ODC.2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 30 df41 ATTACHMENT A Page 2 of 4 LIQUID SOURCE TERMS 1-134 Cs-134 1-135 Cs-136 Cs-137 Ba-137m Ba-140 La-140 Ce-141 Ce-143 Ce-144 Pr-143 Pr- 144 H-3 TOTALO')8.OE-5 4.6E-2 4.3E-3 8.9E-3 3.3E-2 3.1 E-2 1.1 E-4 1.1 E-4 5.1E-5 2.8E-6 3.2E-5 2.7E-5 3.2E-5 5.50E+2 4.05E-1 4E-3 9E-6 3E-4 6E-5 1E-5 1 E-5 8E-5 9E-5 3E-4 2E-4 3E-5 2E-4 6E-3 1 E-2 2.70E+8 1.99E+8 1.19E+8 2.80E+8 8.01 E+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)IP (1)(2)(3)(4)(5)Excluding Tritium and Entrained Noble Gases Source Term for (RM-ILW-104 and RM-1LW- 116) from Stone and Webster Calculation Package UR(B)-160 (.1.1.6)ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 (3.1.3)1.Detection Efficiency for (RM-ILW-104 and RM-ILW- 116) from Calculation Package ERS-SFL-92-039 (3.1.14)Insignificant I Beaver Valley Power Station ProedureNbODC-2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1_ 5 31 of 41 ATTACHMENT A Page 3 of 4 LIQUID SOURCE TERMS TABLE 1.1-1b BV-2 LIQUID SOURCE TERM I*NUCLIDE 2Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Z7r.6 5 (3.1.3.13) Np-239 Br-83 Br-84 Rb-86 Sr-89 Sr-90 Srl91 Mo-99 Tc-99m Te-125m Te-127m Te-127 Te-129m 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 (2)VNNUAL REEASE 1.006-4 250E-5 1.30E-4 650E-5 1.10E-3 1.60E-4 5.10E-2 320E-5 2.90E-5 5.90E-9 3.70E-5 2.20E-5 8-50E-7 530E-6 2.30E-3 2.1OE-3 1.90E-6 2 10&5 2,50E-5 8.20E-5 530E-5 230E-4 520E-5 9.40E-6 1.0OE-1 7.80F,4 230&-3 6.50E-2 4.60E,6 3.OOE-2 9.20E-3 3.90E-3 2.20E-2 2.10E-2 930E-6 8.40E-6 (3)OEC, 5E-3 35-4 113-3 1E-4 2E-4 3E-5 5FE-5 2E-4 9E-3 4E-3 7E-5 8E-5 5E-6 2E.4 2E-4 1E-2 2E-4 9E-5 IE-3 7E-5 4E-3 25-4 813-5 8E-4 LB-5 9E-5 1E-3 7E,.5 4E-3 9E-6 3E-4 6E3-5 113-5 IE-5 8E3-5 9E3-5 (4)DEVIBZON EFFICIENCY 2.01E+7 127E+8 (5)126E+8 1.82E+8 238E+8 65013+7 1.65E+8 2.42E+,6 138E+8 1.04E+7 1.83E+4 (5)1.04E+8 4.47E+7 1.40E+8 3.94E+5 1.26E+5 2.43E+6 6.53E+6 1.96E+7 5.18E+8 2.85E+8 1.88E+8 1.96E+8 1.76E+8 422E+8 1.73E+8 4.06E+8 32+5E+8 1.71E+8 4.28E+8 1.28E+8 133E+8 7.50E+7 3.08E+8 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_5 32U Of 41 ATTACHMENT A Page 4 of 4 LIQUID SOURCE TERMS TABLE 1.1-l b (continued) BV-2 LIQUID SOURCE TERM (2)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(')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 3E-4 3E-4 3E-5 6E-2 3E-4 2E-4 3E-5 2E-4 6E-3 1 E-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)0il (1)(2)(3)(4)(5)Excluding Tritium and Entrained Noble Gases Source Term for (2SGC-RQ 100) from Computer Code LIQ 1BB (3.1.2.3)ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 (3.121)Detection Efficiency for (2SGC-RQ100) from Calculation Package ERS-SFL-86-026 (3.1.2.2)Insignificant Beaver Valley Power Station 1/2-0DC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1_5 33 of 41 ATTACHMENT B Page 1 of 2 RECIRCULATION TIMES TABLE 1.2-la BV-I RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPROXIMATE RECIRCULATION TIME(')TANK DESCRIPTION ASSET NO. (Based on Historical Recirculation Rates)Laundry And Contaminated lLW-TK-6A/6B 2.5 hrs -(1200 gal) (2) / (16 gpm)Shower Dain Tanks Low Level Waste Drain Tanks 1LW-TK-3A/3B 1.5 hrs (2000 gal) (2) / (45 gpm)High Level Waste Drain Tanks 1LW-TK-2A/2B 3.4 hrs (5000 gal) (2) / (50 gpm)Respirator Test Tanks ILW-TK-5A/5B 1.4 hrs (3000 gal) (2) / (73 gpm)Steam Generator Drain Tanks ILW-TK-7A/7B 17.2 hrs -(35000 gal) (2)/(68 gpm)Boron Recovery Test Tanks IBR-TK-2A/2B 9.7 hrs =(13,000 gal) (2)/(45 gpm)(0.The'times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical recirculation rates). Recirculation times for a'partially full tank are directly proportional to the fraction of the tank capacity occupied by the entrained liquid waste (after isolation). Actual recirculation times are determined prior to sampling using actual tank volumes and actual recirculation rates available in the BV-1 Control Room. Beaver Valley Power Station Procedure Number: Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Number: ATTACHMENT B Page 2 of 2 RECIRCULATION TIMES TABLE 1.2-lb BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPROXIMATE RECIRCULATION TIME(" TANK DESCRIPTION ASSET NO. (Based on Historical RecirculationRates) Liquid Waste Tanks 2LWS-TK21A/21B 11.5 hrs = (10,000 gal) (2)/(29 gpm)Steam Generator Blowdown 2SGC-TK21A/21B 25.8 hrs = (51,000 gal) (2)/(66 gpm)ý, Hold Tanks Steam Generator Blowdown 2SGC-TK23A/23B 9.1 hrs = (18,000 gal) (2)/(66 gpm)Test Tanks (1) The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical recirculation rates). Recirculation times for a partially full tank are directly proportional to the fraction of the tank capacity occupied by the entrained liquid waste (after isolation). Actual recirculation times are determined prior to sampling using actualtank volumes and actual recirculation rates available in the BV-2 Control Room. Beaver Valley Power Station Proedre-umer 1/2=ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 5 35 of 41 ATTACHMENT C Page 1 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/ml)NLULDE BONE LIVER T-BODY TIHYROID KIDNEY LUNG GI-I_.H-I-3 -0.00E-01 2701301 27013-01 2.70E501 2.70E-01 2.701301 2701.01 C-14 3.13E04 626E03 626E03 626E03 626E03 626E03 626E03 Na-24 4.08E02 4.08E02 4.081302 4.08E102 4.08E102 4.08E02 4.08E102 P-32 4.62E07 287E06 1.79E06 0.00F_01 0.001E-01 0.0013-01 5.19E06 0r-51 0.005E,1 0.00F_.01 127E00 7.62E-01 281F_,01 1.69E00 321E02 Mn-54 0.0_E-01 438E03 835E02 0.00F_,01 130E03 0.00E-01 134E04 Mn-56 0.00E301 1.10E02 1.951301 0.00E-01 1.40E02 0.00F_01 352E03 Fe-55 6.59E02 456E02 1.06E02 0.00E01 0.00F_.01 2.54E02 261E02 Fe-59 1.04E03 245E03 938E02 0.00E.01 0.001-01 6.83E02 8.15E03 Co-57 0.0013,01 2.10101 350E01 0.00E-01 0.00E-01 0.00F_501 533E02 Co-58 0.00E301 8.95E01 201E02 0.00F__01 0.0013-01 0.00E-01 1.81E03 Co-60 0.00E-01 257E 02 5.67E02 0.0013-01 0.00E,01 0.00E-01 4.83E103 Ni-63 3.12E04 216E03 1.05E03 0.00F_.01 0.00E101 0.0013,01 451E02 NMI65 1.27E02 1.651301 751E00 0.001301 0.00E-01 0.001.01 4.17E02 CV-64 0.001F01 1.00E01 4.70E00 0.005)01 252E01 0.001.01 8.53E02----------------------------------.. ..............................................................................Zn-65 232E04 737E04 333E04 0.001E.01 4.93E04 0.0013-01 4.64E04 Zm69 493E01 9.43E01 656E00 0.00E-01 6.13E01 0.00E,01 1.42E01 Br-83 0.00E-01 0.00E-01 4.04E01 0.001F_0I 0.00E.01 0.0013501 5.82E01 Br-84 0.00E-01 .0.00&-01 524E101 0.001E-01 0.003,-01 0.00E-01 4.1113E04 Br-85 0.00E.01 0.001E-01 215E00 O.OOE0,, 0.00&01 0.00E-01 .0.)00-01 Rb-86 0.00F_601 1.01E05 4.71E04 0.FOOE01 0.003E,01 0.OOE-01 1.99E 04 Rb-88 0.005, 1 2-90E02 154E02 0.003, 01 0.005.01 0.00B101 4.00E109 Rb-89 0.001DOM 1.92E102 135E102 0.00E-01 0.00F_01 0.00E-01 1.12E,-11 Sr-89 222E04 0.00E-.01 639E02 0.00E-01 0.00E-01 0.00F01 357E03 Sr-90 "5.48E05 0.003E,01 134E05 0.00F_)01 0.00F__01 0.00F_01 158E04 Sr-91 4.10E02 0.001.01 1.65E01 0.00F_,01 0.00E-01 0.00E.,01 1.95E03 Sr-92 1.55E02 0.001-01 6.72E100 0.00F01 0.00E3-01 O.0013)01 3.08E03 Y-90 5.80E-01 0.00E3-01 15513F02 0.0013-01 0.00E-.1 0.0013-01 6.15E03 Y-91m 5.48F1,03 0.001301 21213.04 0.001-01 "0.003,01 0.0013-01 1.61E-02 Y-91 8.50E00 0.0013.-01 2.27E301 0.0013E01 0.00E-01 0.00E.01 4.68E03 Y-92 5.09E302 0.0013-01 1.49F_-03 0.0013-01 0.003E,01 0.001)-01 8.92E102 Y-93 1.625.01 0.00' 01 4.46E103 0.00F_-01 0.001_.01 0.00F_01 5.12E03 Zr-95 2.53E-.01 8U IF.,02 5.49F_02 0.00E-01 127E3-01 0.00F01 257E102 Zr-97 1.40AE02 282F_.03 1.29E-03 0.00F_.01 42613.03 0.0013,01 8.73E02 Nb-95 4.47E00 Z49E00 134E100 0.00F01 246E100 0.001-01 151E04 NbW7 3.75E02 1 9.49F,03 3.46E,03 0.001E01 1.11LE-02 0.001.01 3.50E01 Procedure Number: Beaver Valley Power Station 1/2-ODC.2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference,*: ODCM: LIQUID EFFLUENTS Revisio5.w Page Number: , ,5 316-of 41 ATTACHMENT C Page 2 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/ml)NUCL.DE BONE LIVER T-BODY THYROIDI KIDNEY LUNG GI-LL Mo-99 0.OOE-0l 1.05E02 2.00E01 0.00E,01 238E02 0.001,01 2.43E02 Tc-99m 8.97B303 2.5413,02 3.23E-01 0.0013-01 3.85FA01 12413.02 150E01 To-101 923EM0 13313-02 130E-01 0.00E,01 239F.,01 6.79E,03 4.00E-14 Ru-103 4.51E00 0.00E.01 1.94E100 0.00 01 1.72E01 0.0013-01 526E02 Ru-105 3.75E-01 0.001301 1.4813-01 0.00E.01 4.85E100 0.001- 01 229E102 Ru-106 6.70E101 0.0013.01 8.48E00 0.001F30 129E102 0.001.01 4.34E03 Ag-1 10m 9.48E-01 8.77E101 5211-01 0.00E-01 1.72E100 0.001-01 3.58E02 Sb-124 7.87E00 1.49E-01 3.12E00 191E-02 0.001-01 6.13E00 223E02 Sb-125 5.03E00 5.62E102 120E00 5.11E-_03 0.00E101 3.88E00 554E01 Te-125m 257E03 930E02 3.44E02 7.72E02 1.04E04 0.00F,)01 1.03E04 Te-127m 6.49E 03 232E03 7.90E 02 1.66E03 2.63E04 0.00E-01 2.17E04 Te-127 1.05E102 3.78E01 2.28E01 7.81E01 429E102 0.00E301 832E103 Te-129m 1.10E04 4.11E03 1.74E03 3.78E03 4.60E04 0.00E-01 5.55E04 Te-129 3.01E01 1.13E01 733E00 231I01 126E302 0.00E.01 227E01 Te-131m 1.66E03 8.10E02 6.75E02 128E103 821103 0.00E,01 8.05E04 Te-131 1.89E01 7.88100 5.96E00 155E01 827E01 0.00F,-01 2.67E00 Te-132 241E03 1.56E103 1.47E03 1.72E03 150E04 0.00E-01 739E04 Te-134 3.10E01 2.03E01 1251301 2.71101 i.96E 02 0.00F_.0I 3.44E.02 1-129 1.19E02 1.021302 335E02 2.63E05 2.19E02 0.0013,01 1.61E01 1-130 2.75E01 8.10E01 3.20E01 6.871E03 1261302 0.00E-01 6.97E01 1-131 151E02 2.16E02 124E02 7.08E04 3.71.E02 0.00E-01 5.70E01 1-132 737E00 197E01 690E100 6.90E 02 3.14E01 0.003E-01 3.71E00 1-133 5.16E01 8.97E101 2.74E01 132E04 1.57E02 0.003E,01 806101 1-134 3.85E00 1.05E01 3.74E100 1.81E02 1.66E01 0.00E-01 9.12B.03 1-135 1.61E01 421E101 155E01 2-78E103 6.76E01 0.001301 4.76101 Cs-134 298E05 7.09E05 5.79E05 0.00E-01 2.29E05 7.61E(4 124E04 Cs-136 3.12E 04 123E05 8.86E04 0.00E-01 6.85EO4 939E03 1.40E14 Cs-137 3.8230O5 522EO"5 34213O5 0.O0F0.01 1.77105 5.89E 04 1.01E04 Cs-138 2.64E02 5.22102 2.59E102 0.00E-01 3.84E02 3.79E01 22.31-03 Ba-139 9.691,-01 6.901304 2.84E-02 0.001-01 6.45E1-04 392E-04 1.72E00 Ba-140 2031EO32 2.55101 133101 0.001E301 8.661E02 1.46101 Ba-141 4.713E-01 356.04 1.591302 0.001301 33113.04 2.021-04 2221,-10 Ba-142 2.131E01 2.19E-04 1341302 0.001.01 1.85E-04 1241304 3.00119 La-140 1.511,01 7591302 20113-02 0.00301 0.001 0.001.01 5E571E3 La-142 7.711E303 351E303 8.741-04 0.001E301 0.0013.01 0.00101 256101 Co-141 2.63102 1.78E-02 2.021303 0.001301 826130 0.001E301 6.80E01 Beaver Valley Power Station Procedure Number: B e l P r t1/2-ODC-2.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1 1 5 37 of 41 ATTACHMENT C Page 3 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-i Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/ml)NUCLIDE Ce-143 Ce-144 Pr-143 BONE 4.64E-03 137E00 5.54E-01 LIVER T-BODY THYROID KIDNEY LUNG 3.43E00 5.73E-01 2.22E-01 3.79E-04 736E-02 2.751302 0.OOE-O1 0.00E-01 0.OOE-01 1.51E-03 3.40E_01 128E.01 0.OOE-01 O.00E-01 0.OOE-01 GI-LLI 1.28E02 4.64E02 2.43E 03 Pr-144 1.81E-03 7.53E-04 9.22E05 0.OOE-01 4.25E-04 0.00E-01 2.61E-10 Nd-147 3.79E-01 4.38E-01 2.62E-02 0.OOE-01 2.%B601 0.00E-01 2.10E03 W-187 2.96E02 2.47E02 8.65E01 0.00E-01 0.0013-01 0.00E-01 8.10E04 Np-239 2.90E-02 2.85E-03 1.57E-03 0.OOE-01 8.89E-03 0.001-01 5.85E 02 Beaver Valley Power Station I Procedure Number: I Title: Unit: Level Of Use: 1/2 [General Skill Reference ODCM: LIQUID EFFLUENTS Revision: [Page Number: 5 1 2,A ATTACHMENT D Page 1 of 3 LIQUID RADWASTE SYSTEM STREAM Containment Sump UNIT 1: COLLECTION, TREATMENT,.& DISCHARGE LIQUID WASTE DISCHARGES TO BVPS-1 COOLING TOWER BLOWDOWN AND ENVIRONMENT 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: 5 39 of 41 ATTACHMENT D Page 2.of 3 LIQUID RADWASTE SYSTEM STREAM UNIT 2: COLLECTION, TREATMENT, & DISCHARGE BVPS-1 Cooling Tower Blowdown 15,000 gpm BVPS-2 Cooling Tower Blowdown 7,800 gpm BVPS l&2 Combined Cooling Tower Discharge Point 22,800 gpm LIQUID WASTE DISCHARGES TO BVPS-2 COOLING TOWER BLOWDOWN AND ENVIRONMENT Procedure Number: Beaver Valley Power Station J____ ___ ____ ___ ____ ___ ____ ___ ____ ___ ____ ___ ___1/2-ODC-2.O 1 Title: Unit: Level Of Use: 1/2 General Skill Reference,, ODCM: LIQUID EFFLUENTS Revision: Page Number: 1 -5 40of41 S ATTACHMENT D Page 3 of 3 LIQUID RADWASTE SYSTEM FIGURE 1.4-3 BV-1 AND 2 LIQUID EFFLUENT RELEASE POINTS Beaver Valley Power Station ProceueNub 2 erODC 2 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: LIQUID EFFLUENTS Revision: Page Number: 1 5 41 of 41 ATTACHMENT E Page 1 of 1 SITE BOUNDARY FOR LIQUID EFFLUENTS Figure 5-1 RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.02 ODCM: GASEOUS EFFLUENTS Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 2 Level Of Use In-Field Reference Safety Related Procedure Yes Beaver Valley Power Station Procedure Number: 1/2-ODC-2.02 6 i Title: ODCM: GASEOUS EFFLUENTS Unit: Level Of Use: 1/? I In-Field Reference Revision: Page Number: I I 2 nf lP TABLE OF CONTENTS 1. 0 PURPOSE ........................................................................................................................................ 4 2.0 SCOPE............................................. ...................................... ................................... ............. 4
3.0 REFERENCES
AND COMMITMENTS ....................................... 4 3.1 References .......................................................................................................... 4 3.2 Comm itments ......................................................................................................................... 6 4.0 RECORDS AND FORM S ...................................................................................................... 6 4.1 Records ................................................................................................................................... 6 4 .2 F o rf s ....................................................................................................................................... 6 5.0 PRECAUTIONS AND LIM ITATIONS .......................................... ............................................. 6 6.0 ACCEPTANCE CRITERIA ........................................................................................................ 8 7.0 PREREQUISITES ............................................................................................................................ 8 8.0 PROCEDURE .................................................................................................................................. 8 8.1 Alarm Setpoints...................................................................................................................... 8 8.1.1 BV-1 M onitor Alarm Setpoint Determination ...................................................... 8 8.1.2 BV-2 M onitor Alarm Setpoint Determ ination ............................................... 18 8.1.3 BV-1/2 Monitor Alarm Setpoint Determination ...................... 28 82 Compliance With 10 CFR20 Dose Rate Linits (ODCM CONTROL 3.112.1) .................................. 35 8.2.1 Dose Rate Due To Noble Gases ...................................................................... 35 8.2.2 Dose Rate Due To Radioiodines And Particulates ......................................... 42 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)(Gaseous) ........ ............................................................................................... ...46 8.3.1 Dose Due To Noble Gases ............................................................................. 46 8.3.2 8.4 Gaseous 8.4.1 8.4.2 ATTACHMENT A ATTACHMENT B ATTACHMENT C ATTACHMENT D ATTACHMENT E ATTACHMENT F ATTACHMENT G ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENT K ATTACHMENT L ATTACHMENT M ATTACHMENT N ATTACHMENT 0 Dose Due To Radioiodines And Particulates ................................................. 53 R adw aste System ................................................................................................... 69 BV-1 Gaseous Radwaste System Components ............................................... 69 BV-2 Gaseous Radwaste System Components .................................................. 70 GASEOUS SOURCE TERM ........................ .......... 72 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES ........... 74 MODES OF GASEOUS RELEASE ...................................
- ...............................
76 RA DION UCLIDE M IX .................................................................................. 77 DISTANCES TO RELEASE POINTS ............................ 79 0-5 MILE DISPERSION PARAMETERS ...................................................... 80 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS .................... 87 ORGAN DOSE PARAMETERS ................................................................... 89 MODES OF GASEOUS RELEASE ............................................................... 90 P&I ORGAN DOSE FACTORS ................................................................... 91 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES). .... 110 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL D IST A N C E S) ....................................................................... ............................. 117 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL D IST A N C E S) .................................................................................................... 124 BATCH RELEASE DISPERSION PARAMETERS (0 -5 MILES) ....... 127 GASEOUS RADWASTE SYSTEM ................................................................. 128.1 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOU S EFFLUENTS Revision: Page Number:___ ___ __ ___ __ ___ __ ___ ___ __ ___ __ ___ __ 2 3 of 110 TABLE OF CONTENTS ATTACHMENT A ATTACHMENT B ATTACHMENT C ATTACHMENT D ATTACHMENT E ATTACHMENT F ATTACHMENT G ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENT K ATTACHMENT L ATTACHMENT M ATTACHMENT N ATTACHMENT 0 ATTACHMENT P ATTACHMENT Q GASEOUS SOURCE TERM ........................................................ 72 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES............ 74 MODES OF GASEOUS RELEASE................................................. 76 RADIONUCLIDE MIX ........... .................................................... 77 DISTANCES TO RELEASE POINTS............................................... 79 0-5 MILE DISPERSION PARAMETERS........................................... 80 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS.................. 87 ORGAN DOSE PARAMETERS .................................................... 89 MODES OF GASEOUS RELEASE ................................................. 90 P&I ORGAN DOSE FACTORS..................................................... 91 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)....110 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)......................................................................... 117 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES) ........................................................................ 124 BATCH RELEASE DISPERSION PARAMETERS (0 -5 MILES)............ 127, GASEOUS RADWAST]8 SYSTEM ............................................... 128 By-I AND BV-2 GASEOUS EFFLUENT RELEASE POINTS................ 129 SITE BOUNDARY FOR GASEOUS EFFLUENTS ............................. 130 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 4_of 1302 1.0 PURPOSE 1.1 This procedure provides the calculational methodology to be used for determination of the following release parameters.
1.1.1 Gaseous
effluent monitor alarm setpoints 1.1.2 Gaseous effluent dose rate calculations
1.1.3 Gaseous
effluent dose calculations 1.2 This procedure also provides information related to the following:
1.2.1 Gaseous
Radwaste Treatment System.1.2.2 Site Boundary used for gaseous effluents.
1.3 Prior
to issuance of this procedure, these items were located in Section 2 and Section 5 of the old ODCM.2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS
3.1 References
3.1.1 References
for BV-1 Gaseous Effluent Monitor Setpoints 3.1.1.1 Beaver Valley Power Station, Appendix I Analysis -Docket No. 50-334 and 50-412; Table 2.1-3 3.1.1.2 Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-1 3.1.1.3 BVPS Specification No. BVS 414, Table V Nuclide Data,; Table I and Figure 1, Table 3, and Figure 2, May 30, 1974 3.1.1.4 Calculation Package No. ERS-SFL-85-03 1, Unit 1 Gaseous Effluent Monitor Efficiency Data 3.1.1.5 Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.1.6 Calculation Package No. ERS-ATL-87-026,BVPS-1 and BVPS-2 ODCM T Factor Justification I Beaver Valley Power Station Procedure Number: 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number.1_2 ____5 of 130 3.1.1.7 Letter NDISHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B 3.1.1.8 Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.2 References for BV-2 Gaseous Effluent Monitor Setpoints 3.12.1 Calculation Package No.ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies 3.1.2.2 Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.2.3 Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-2 3.1.2.4 Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification 3.1.2.5 Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps" 9 3.1.3 References Used for other portions of this procedure 3.1.3.1 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)3.1.3.3 NUREG-0324; XOQDOQ Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations, September 1977 3.1.3.4 NUREG-00 17; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents form PWR's Revision 0.3.1.3.5 Regulatory Guide 1.109, Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I, April 1977 3.1.3.6 NUREG-0172, Age -Specific Radiation Dose Commitment Factors for a one-year Chronic Intake 3.1.3.7 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.3.8 1/2-ADM-0 100, Procedure Writers Guide 3.1.3.9 NOP-SS-3001, Procedure Review and Approval ,Procedure Number:p B e a v e r V a lley P o w e r S tatio n I c 1/2 -ONC -2 .02____________________________________________1/2,-OOC-2.02 Title: Unit: -Level Of Use: ,1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: IDM AEU FLET 2 6 6of 130' :.3.1.3.10 CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit 1 Containment Vacuum Pump Source-Term in ODCM procedure 1/2-ODC-2.02, Attachment A, Table 2.1-la.3.1.3.11 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.CA-16, Revise procedure 1/2-ODC-2.02 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental &.Chemistry. 3.1.3.12 Unit 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, 2006.3.1.3.13 Vendor Calculation Package No. 8700-UR(B)-223, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternative Source Terms on the Alarm Setpoints for the Radiation Monitors at Unit 1.3.1.3.14 Engineering Change Package No. ECP-04-0440, Extended Power Uprate.3.1.3.15 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-0Z; revise ODCM procedure 1/2-ODC-2'.02 to update the alarm setpoints of gaseous effluent radiation monitor for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275.3.2 Commitments 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 ODCM CONTROLS applicable to dose rate apply to the site. The site dose rate is due to the summation of releases from both units.5.2 ODCM CONTROLS applicable to accumulated dose apply individually to each unit. p Procedure Number: yPower Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 2 1 7 of 130 5.3 Releases at the Beaver Valley site may be ground level or elevated in nature.5.3.1 All ground level releases are identified with a specific unit in the determination of site dose rate and dose attributed to that unit.5.3.2 Elevated releases from both units are considered to originate from a shared radwaste system and are discharged from a common release point, the Process Vent, at the top of the BV-1 cooling tower.5.4 At BV-1 and BV-2, the dose from continuous and batch (Gas Waste Storage Tanks) releases via the ýhared radwaste system (Process Vent) are normally apportioned equally to the units.Other continuous and batch releases via non-shared radwaste systems shall be attributed to a specific unit. The only exception is a containment purge via the Process Vent which shall be attributed to a specific unit.5.5 There is a difference in setpoint terminology presentations of the radiation monitoring systems of BV- I and BV-2.5.5.1 Where HIGH and HIGH-HIGH terminology are used for the BV-1 Victoreen monitors, ALERT and HIGH terminology are used for the BV- 1 Eberline SPING monitors and the BV-2 monitors.5.5.2 Also, BV-2 setpoints are presented in uCi/cc rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to the BV-2 raw data (cpm). The user is cautioned that the uCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice, setpoints determined for a calculated mix are correct for that mix. Setpoints determined on analysis prior to release will be correct for properly controlling dose rate, but the indicated uCi/cc value may differ from the actual value.5.5.3 All BV-1 and BV-2 effluent monitors specified herein have Upper Alarm Setpoints established at 60 percent of the site limit, and Lower Alarm Setpoints established at 30 percent of the site limit.5.6 A release may be batch or continuous in nature. Batch refers to. releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment purges and ventings of systems or components with infrequent use.5.6.1 Batch releases may be due to operational variations which result in radioactive releases greater than 50% of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of 500 hours or less in a calendar year, but not more than 150 hours in any quarter.5.6.2 The batch relative concentration value has been calculated in accordance with the guidelines provided in NUREG-0324(31 3 3) for short-term release. Beaver Valley Power Station ProcedureNu11/2IODC.2.02 Title: Unit: Level Of Use: 1/L2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2_8_of 130 5.6.3 IF simultaneous batch and continuous release out of one vent occurs, THEN use the lowest setpoint obtained according to Sections 8.1.1.1 through 8.1.3.2.5.7 This procedure also contains information that was previously contained in Section 5 of the previous BV-l and BV-2 Offsite Dose Calculation Manual.5.7.1 In regards to this, the site boundary for gaseous effluents was. included in this procedure. 5.7.2 The Site Boundary for Gaseous Effluents is shown in ATTACHMENT P Figure 5-1.6.0 ACCEPTANCE CRITERIA 6.1 All changes to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy of effluent dose or alarm setpoint calculation. (3.1.3.2)6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3".' 3"s)and 1/2-ADM-1640. (3.1.3.7)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-300 1(3.1.3.9) and 1/2-ADM- 1640. (3.1.3.7)7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.8.0 PROCEDURE 8.1 Alarm Setpoints 8.1.1 BV-1 Monitor Alarm Setpoint Determination ODCM CONTROL 3.11.2.1 require that the dose rate in unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site shall be limited to < 500 mremlyr to the total body and to < 3000 mrem/yr to the skin.This section describes the methodology used to maintain the release of noble gas radionuclides within ODCM CONTROL 3.11.2.1 for the site, and determines monitor setpoints for BV-1.The methodologies described in Section 8.1.1.2, 8.1.2,2, and 8.1.3.2 provide an alternate means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release. A, Control of the site dose 'rate limit due to noble gases is shown in the following Table. Dose rate control is exercised through a total of 8 effluent stream monitors, of which 3 are Procedure Number: Beaver Valley Power Station l/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:, Page Number: 2 9_6f_130 located at BV-1 (alternates exists for these monitors), and 5 are located at BV-2. As previously noted, BV-I and BV-2 elevated releases are via the PV-1/2 Process Vent.Monitor Setpoint Specifications Based On Fraction Of Site Limit UNIT RELEASE POINT F MONITOR NO. U (VV-1) Unit 1, Auxiliary Building Vent Pri.: RM-1VS-101B or 61 Alt.: RM-1VS-109 (5) 64 RACTION OF SITE LIMITING DOSE RATE*pper Alarm 0% (HIGH-HIGH) 0% (HIGH)(CV- 1). Unit 1, R.X Containment/SLCRS Vent Pri.: RM-IVS-107B or 60% (HIGH-HIGH) Alt.: ,RM-IVS- 110 (5) 60% (HIGH)(PV-1/2), Unit 1/2, Gaseous Waste/Process Vent Pri.: RM- 1GW- 108B or 60% (HIGH-HIGH) Alt.: RM-1GW-109 (5) 60% (HIGH)(CV-2), Unit 2, SLCRS Filtered Pathway.2HVS-RQ109E 60% (HIGH)(VV-2), Unit 2, SLCRS Unfiltered Pathway 2HVS-RQ1OIB 60% (HIGH)(WV.-2), Unit 2, Waste Gas Storage Vault Vent 2RMQ-RQ303B 60% (HIGH)(DV-2), Unit 2, Decontamination Building Vent 2RMQ-RQ301B 60% (HIGH)(CB-2), Condensate Polishing Building Vent 2HVL-RQ1 12B 60% (HIGH)Lower Alarm 30% (HIGH)30% (ALERT)30% (HIGH)30% (ALERT)30% (HIGH)30% (ALERT)30% (ALERT)30% (ALERT)30% (ALERT)30% (ALERT)30% (ALERT)With the monitor setpoints based on fractions of the site limit as defined above, the foll6wing criteria may be applied to determine that the dose rate due to noble gas released from the site complies with ODCM CONTROL 3.11.2.1: " The site dose rate is 30% of the site dose rate limit when any monitor is indicating a Lower Alarm.The site dose rate is 60% of the site dose rate limit when any two monitors are indicating Lower Alarms.The site dose rate is 60% of the site dose rate limit when any monitor is indicating an Upper Alarm.The site dose rate is 90% of the site dose rate limit when any monitor is indicating an Upper Alarm and any other monitor is indicating a Lower Alarm. Beaver Valley Power Station ProceoureNumber: Title: Unit: Level Of Use: 1/2 I In-Field Reference A 4-ODCM: GASEOUS EFFLUENTS Revision: Page Number:.I I M f1Th r-T L -8.1.1.1 BV-I Setpoint Determination Based On A Calculated Mix For W-1 and CV-1 Ground Releases The table below gives the calculated monitor count rate above background (CR), in ncpm, and provides the equivalent monitor indication associated with the most limiting site dose rate limit (i.e.; 500 mrem/yr Total Border or 3000 mrem/yr skin).The monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP)ý for each vent and operational condition shall be as follows: BV-I ALARM SETPOINTS FOR GROUND RELEASES cpm ABOVE BACKGROUND
- Continuous Release Via The BV- I Auxilary Building Vent (VV-1)* Batch Release Of Containment Purge Via The BV-I Auxiliary Building Vent (VV-1)" Continuous Release Via The BV- 1 Rx Containment/SLCRS Vent (CV-1)* Batch Release Of Containment Purge Via The BV- I Rx Containment/SLCRS Vent (CV-1)(P) PRIMARY*MON1TOR (A)ALTERNATE MONITOR (P)RM-IVS-101B (A)RM-IVS-109(5)(P)RM-1VS-101B (A)RM- 1 VS- 109(5)(P)RM-1VS-107B (A)RM-1 VS-1 10(5)(P)RM-1VS-107B (A)RM-1 VS-1 10(5)CR 3000 1470 1200 1430 6440 3380 12,700 6660 60%LIMIT UPPER ALARM,_< 1800< 879:<718< 860< 3870< 2030-< 7630-< 4000 30%SITE LIMIT UPPER ALARM-< 900< 440-<359-< 430< 1930:< 1010<3810< 2000*IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for* the respective alternate monitor. The alternate setpoints shall be utilized.The setpoints were determined using the following conditions and information:
0 Source terms given in ATTACHMENT A Table 2.1-1 a. The gaseous source terms were derived from Stone & Webster computer code GAS 1 BB (similar to NUREG-001 1 and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-l a does.not include particulates and iodines, which are not used in site noble gas dose rate calculations.
- Onsite meteorological data for the period January 1, 1976 through December 31, 1980.* Discharge flow rate of 62,000 cfm for a VV-1 Continuous Release.I.." 9 Beaver Valley Power Station Procedure Number: B1/2-ODC-2.02 Title:
- Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASIFOUS EFFLUENTS Revision:
Page Number:.--2 11 of 130*: Discharge flow rate of 92,000 cfm for a VV- 1 Batch Release of Containment Purge.This is comprised of 30,000 cfm from. the containment purge plus 62,000 cfm for VV-1.Discharge flow-rate of 49,300 cfm for a CV-1 Continuous Release.* Discharge flow rate of 56,800 cfm for a CV- 1 Batch Release of Containment Purge.This is comprised of 7,500 cfm from the containment purge plus 49,300 cfm for CV- 1.* Information listed under References for BV-I Gaseous Effluent Monitor Setpoints. ThO calculation method given in Sections 8.1.1.1.1 through 8.1.1.1.7 was used to derive the monitor setpoints for the following operational conditions: " Continuous release via VV-1.* Continuous release via CV- 1.* Batch release of BV-I Containment Purge via VV- 1.* Batch release of BV-1 Containnient Purge via CV-2.8.1.1.1.1 BV-1 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows: " The gaseous source terms that are representative of the "mix" of the-gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-l a." The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide 'T' (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by: Si= A, ZA,[2.1(1)-1] where: Ai = The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la. Procedure Number: Beaver Valley Power Station .1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference m ODCM: GASEOUS EFFLUENTS Revision-Page Number: 2 12 of 130 8.1.1.1.2 BV-1 Maximum Acceptable Release Rate (Whole Body Exposure)The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by: 500 Qt = [2.1(1)-2](X/Q) XK 1 S 1 where: (X/Q)wV The highest calculated annual average relative concentration of effluents released via VV- 1 for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT F Table 2.2-5..1.03E-4 sec/mr 3 for continuous releases.(X/q)vv The highest calculated short term relative concentration of effluents released via VV- 1 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT M Table 2.3-36.= 3.32E-4 sec/mr 3 for batch release of containment purge.(X/Q)CV The highest calculated annual average relative concentration of effluents released via CV- 1 for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT F Table 2.2-4.9.24E-5 sec/mr 3 for continuous releases.(X/q)cv = The highest calculated short term relative concentration of effluents released via CV-1 for any area at or beyond the unrestricted area boundary for any sectors (sec/mr 3) from ATTACHMENT M Table 2.3-35.= 3.08E-4 sec/mr 3 for batch release of containment purge.Ki = The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11. __Si= From equation [2.1(1)-I]
above. Beaver Valley Power Station ProcedurNumber: 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 11 6f 130 8.1.1.1.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure)Qtwas also determined based upon the skin exposure limit by: Qt= (X/Q)Z 3000 .M;(Li + 1.1Mi) Si where: Li The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.Mi = The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.1.1 = The ratio of the tissue to air absorption coefficients over the energy iange of the photons of interest, (mrem/mrad).(X/Q) = Same as in Section 8.1.1.1.2.
BV-1 Maximum Acceptable Release Rate (Individual Radionuclide) 8.1.1.1.4 The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by: Qi =Si Qt [2.1(1)-4] NOTE: Use the lower of the Qt values obtained in Section 8.1.1.1.2 and 8.1.1.1.3. -Procedure Number: Beaver Valley Power Station 1roc0 C02.m ,___ __ ___ __ ___ __ ___ __ __ ___ __ ___ __ ___ __ ___ __ _1/2,ODC-2.02. Title Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 14 of 130 ...8.1.1.1.5 BV-1 Maximum Acceptable Concentrations (Individual Radionuclide) The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide "i" in the gaseous effluent was determined by: Ci= 2.12E-3 Qj [2.1(1)-5] F where: F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.1.1.2.12E-3 = Unit conversion factor (60 sec/min x 3.53E-5 ft3/cc).8.1.1.1.6 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide. CR was determined by: CR= ZCiEi [2.1(1)-6)] where: Ei = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.8.1.1.1.7 BV-1 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:* The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by: HHSP = 0.60 x CR [2.1(1)-7] 0 The monitor HIGH Alarm Setpoint above background (ncpm) was determined by: HSP = 0.30 x CR [2.1(1)-8] NOTE: The values 0.60 for the HHSP and 0.30 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not -.-exceeded due to simultaneous releases from both units. Procedure Number: Beaver Valley Power Station eNl/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 15 of 130 8.1.1.2 .BV-1 Setpoint Determination Based On Analysis Prior To Release For VV-1 and CV-1 Ground Releases When the setpoints established using "the calculated mix" for ground releases do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Step 8.1.1.1. In this case, the results of sample analysis are used to determine the source term "mix." This calculational method applies to gaseous releases via VV-l and CV-l when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm-Setpoint based on this flow rate during the following operational conditions:
- Batch release of Containment Purge via VV-1." Batch release of Containment Purge via CV- 1 8.1.1.2.1 BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV- 1 and CV- 1 during purging is determined as follows: The maximum acceptable gaseous discharge flow rate (f) from VV-1 and CV-1 (cfm) during purging based upon the whole body exposure limit is calculated by: 1.06 S T 1.06 S [2.1(1)-17](X/q) Ki Ci where: 1.06 500 mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit 2.12E-3 = unit conversion factor= (60 sec/min x 3.53E-5 ft 3/cc)S Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 8.1.1.T Maximum valve for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16).(3""6)
Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 16_of 130 (X/q)w The highest calculated short term relative concentration of effluents released via VV- I for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT M Table 2.3-36.3.32E-4 sec/mr 3 (X/q)cv The highest calculated short term relative concentration of effluents released via CV-1 for areas at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT M Table 2.3-37.-3.08E-4 sec/mr 3 Ki The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.Ci The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.o The flow rate (f) is also determined based upon the skin exposure limit as follows: 6.365ST 6.6= [2.1(1)-18](X/q) + 1.1M) Ci where: 6.36 = 3000 mrem/yrx 2.12E-3 3000 mremryr = dose rate limit 2.12E-3 = unit conversion factor= (60 sec/min x 3.53E-5 ft 3/cc)Li = The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrern/year/uCi/m
- 3) from ATTACHMENT G Table'2.2-11.Mi= The air dose factor due. to gamma emissions from noble gas radionuclide "i" (mradiyear/uCi/m
- 3) from ATTACHMENT G Table 2.2-I1.(X/q) = Same as above.
Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 17 of 130* The flow rate (f) is determined by selecting the smaller of the calculated (f)values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.8.1.1.2.2 BV-1 Monitor Setpoints* The monitor alarm setpoints above background are determined as follows:* The calculated monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attributed to noble gas radionuclides is determined by: f Z Ci E 1 HHSP = F' [2.1(1)-191 where: f The maximum acceptable gaseous discharge flow rate (cfm)determined in Section 8.1.1.2.1. F' The maximum actual or design effluent flow rate (cfm) at the point of release.92,000 cfm for VV-1= 56,800 cfm for CV-1 C i The undiluted radioactivity concentration of noble gas radionuclide"i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released."Eli = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.When a HIGH-HIGH set point has been calculated according to this section, the monitor HIGH Alarm Setpoint above background (ncpm) is determined as follows: HSP = HHSP x 0.5[2.1(1)-201 BeaerVal Po Procedure Number: 22 Beaver Val,,ey Power Station I 1/2-ODC-2.02/ Title: ODCM: GASEOUS EFFLUENTS Unit: I Level Of Use:.2 In-Field Reference IiA Revision: Page Number: 2 I i offl O.Y 8.1.2 BV-2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determinations. 8.1.2.1 BV-2 SetDoint Determination Based On A Calculated Mix For VV-2. CV-2.DV-2, WV-2 and CB-2 Ground Releases.The table below gives the calculated monitor count rate above background (CR) in ncpm, and provides the equivalent monitor indication (DV) in net uCi/cc associated with the most limiting site dose rate limit (i.e., 500 mrem/yr Total Body or 3000-mrem/yr Skin). The HIGH alarm setpoint.(HSP), in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCi/cc above background for each vent and operational condition shall be as follows: BV2 ALARM SETPOINTS FOR GROUND RELEASES uCi/cc ABOVE BACKGROUND (unless otherwise specified) 60%SITE LIMIT UPPER DV ALARM 30%SITE LIMI4 LOWER ALARM CR ncp~m" Continuous Release Via The BV-2 SLCRS Unfiltered Pathway (VV-2)* Batch Release Of Containment Purge Via The BV-2 SLCRS Unfiltered Pathway (VV-2)* Continuous Release Via The BV-2 SLCRS Filtered Pathway (CV-2)* Batch Release Of Containment Purge Via The BV-2 SLCRS Filtered Pathway (CV-2)* Continuous Release Via The BV-2 Condensate Polishing Building Vent (CB-2)* Continuous Release ViaThe BV-2 Decontamination Building Vent (DV-2)Continuous Release Via The BV-2 Waste Gas Storage Vault Vent (WV-2)MONITOR 2HVS-RQ!O1B 2HVS-RQ1O1B 2HVS-RQ 109E 2HVS-RQ I 09E 2HVL-RQI 12B 2RMQ-RQ301B 2RMQ-RQ303B p 8260 3.01E-4 < 1.81E-4 <9.04E-5 2020 7.39E-5 < 4.43E-5 < 2.22E-5 4320 2940 < 1770 jtCi/sec lRCi/sec< 883 tCi/sec<338 jiCi/sec 16,400 1130< 676 uICi/sec 28,900 1.61E-3 <9.63E-4 <54.82E-4 56,600 3.15E-3 < 1.89E-3 <9.44E-4 912,000 2.58E-2 < 1.55E-2 <7.74E-3 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 19 of 130 The setpoints were determined using the following conditions and information: " Source terms given in ATTACHMENT A Table 2.1-1 b. These gaseous source terms were derived from Stone & Webster computer code GAS 1 BB (similar to NUREG-0017)(. 1.3.4) and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-lb does not include particulates and iodines, which are not used in site noble gas dose rate calculations. -The Containment Building Purge radionuclide mix was utilized for the purposes of determining an alarm setpoint for the' SLCRS Unfiltered Pathway on the basis of the proximity of the contiguous areas." The Decontamination Building and Condensate Polishing Building ventilation exhaust are not expected to be radioactive. However, for purposes of determining an alarm setpoint, it is conservatively assumed that Xe- 133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits.* The Waste Gas Storage Vault ventilation exhaust is also not normally radioactive. However, the monitor alarm setpoint is based on the assumption that the ventilation exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the waste gas storage vault. This spectrum is listed in ATTACHMENT A Table 2.1- lb under Gaseous Waste System." Onsite meteorological data for the period January 1, 1976 through December 31, 1980.*r Discharge flow rate of 23,700 cfm for a VV-2 Continuous Release.Discharge flow rate of 53,700 cfm for a VV-2 Batch Release of Containment Purge. This is comprised of 30,000 cfm from the containment purge plus 23,700 cfm from the CV-2.* Discharge flow rate of 59,000 cfm for a CV-2 Continuous Release.* Discharge flow rate of 59,000 cfm for a CV-2 Batch Release of Containment Purge. This is comprised of 7,500 cfm from the containment purge plus 51,500 cfm from CV-2.* Discharge flow rate of 30,556 cfm for a CB-'2 Continuous Release.* Discharge flow rate of 12,400 cfm for DV-2 Continuous Release.* Discharge flow rate of 2,000 cfm for WV-2 Continuous Release.
- Procedure Number: Beaver Valley Power Station 17o u C,,.o2___________1___________________l2-ODC-2.02 Title: Unit: Level Of Use: I1L2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number: ...,._ 2 20of 130 e Information listed under References for BV-2 Gaseous Effluent Monitor Setpoints. The calculation method given in Sections 8.1.2.1.1 through 8.1.2.1.7 was used to derive the alarm setpoints for the following operational conditions:
- Continuous release via VV-2.* Continuous release via CV-2.* Batch release of BV-2 Containment Purge via VV-2.* Batch release of BV-2 Containment Purge via CV-2.* Continuous release via CB-2.9 Continuous release via DV-2.* Continuous release via WV-2.8.1.2.1.1 BV-2 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows: The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate.
Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-l b.The fraction of the ;total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by: Si- [2.1(2)-1] where: Ai = The radioactivity concentration of noble gas radionuclide 'T' in the gaseous effluent (for VV-2, CV-2 and WV-2) is from ATTACHMENT A Table 2.1-l b. However, SINCE releases via CB-2 and DV-2 do not have a valid source term mix, THEN the noble gas radioactivity concentration is assumed to be Xe-133. Beaver Valley Power Station Procedue Number: Beaver1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 21 of 130 8.1.2.1.2 BV-2 Maximum Acceptable Release Rate (Whole Body Exposure)The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by: Qt = 500 (X/Q) YKi Si![2.1(2)-2] where: (X/Q)v The highest calculated annual average relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-5.(X/q)vv= 1.03E-4 sec/mi 3 for continuous releases.= The short term relative concentration of effluents released via VV-2 for any area ator beyond the unrestricted area boundary for all sectors (sec/mi 3) from ATTACHMENT M Table 2.3-36.= 3.32E-4 sec/m 3 for batch release of containment purge.(X/Q)cv =The highest calculated annual average relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-4.= 9.24E-5 sec/m 3 for continuous releases.(X/q)cv= The short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT M Table 2.3-35.= 3.08E-4 sec/mi 3 for batch release of containment purge.(X/Q)CP =The highest calculated annual average relative concentration of effluents released via CB-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT F Table 2.2-10.= 7.35E-5 sec/m 3 for continuous releases. Beaver Valley Power Station ProcedureNumber:O........" 112-OIDC-2.02 Title:*Unit: Level Of Use:*1/2 In-Field Reference j Revision: Page Number: 2 .9) nf 110 ODCM: GASEOUS EFFLUENTS (X/Q)dv =The highest calculated annual average relative concentration of effluents released via DV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-8.= 9.24E-5 sec/m 3 for continuous releases.(XIQ)wV =The highest calculated annual average relative concentration of effluents released via WV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-9.= 9.24E-5 sec/mr 3 for continuous releases.Ki= The total whole body dose factor due to gamma emissions from noble gas- radionuclide "i" (mrem/year/uCi/m 3)from ATTACHMENT G Table 2.2-11.8.1.2.1.3 Si From equation [2.1(2)-1]. BV-2 Maximum Acceptable Release Rate (Skin Exposure)Qt was also determined based upon the skin exposure limit by: Qt = (XQ)3000 Y (Li + 1.1Mi) Si i[2.1(2)-3] where: Li-The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.The air dose factor due to gamma emissions from noble gas radionuclide
'iT(mrad/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).
1.1 (X/Q)= Same as in Section 8.1.2.1.2. Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 23 of 130 8.1.2.1.4 BV-2 Maximum Acceptable Release Rate (Individual Radionuclide) The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each noble gas radionuclide in the gaseous effluent was determined by: Qi = Si Q t[2.1(2)-4] 8.1.2.1.5 NOTE: Use the lower of the Qt values obtained in Section 8.1.2.1.2 and 8.1.2.1.3. BV-2 Maximum Acceptable Concentrations (Individual Radionuclide) The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide in the gaseous effluent was determined by: 2.12E-3 Qj F[2.1(2)-5] where: F The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.2.1.2.12E-3 = Unit conversion factor (60 sec/min x 3.53E-5 ft 3/cc).8.1.2.1.6 BV-2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (CR) was determined by: CR= ZCi E 1 I[2.1(2)-6)] where: Ei = The detection efficiency of the monitor for noble gas radionuclide "iT (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b. ..... Procedure &umber: t Beaver Valley Power Station P 1/2rODC-2.02 Title: Unit: Level Of Use:.1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:.. .'24 of 8.1.2.1.7 BV-2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows: 0 The monitor HIGH Alarm Setpoint above background (uCi/cc) was determined by: 0.60 x CR HSP= E- e [2.1(2)-7] Ei ae where;Ei ave The CR of equation [2.1 (2)-6] divided by the sum of the Ci for the respective mix.The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by: 0.30 x CR AS' jae[2.1 (2)-8]ASP E = Eave 8.1.2.2 BV-2 Setpoint Determination Based'On Analysis Prior To Release 'or VV-2 and CV-2 Ground Releases When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Section 8.1.2.1. In this case, the results of sample analysis are used to determine the appropriate nuclide mix. This calculational method applies when determining the setpoint for the maximuim acceptable discharge flow rate and the associated HIGH Alarm Setpoint based on respective vent flow rate during the following operational conditions:
- Batch release of Containment Purge via VV-2.* Batch release of Containment Purge via CV-2.=J I.-.11. '....... Beaver Vale Iw SProcedure Number: yPower Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number: 2 25 of 130 8.1.2.2.1 BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-2 or CV-2 during purging is determined as follows:* The maximum acceptable gaseous discharge flow rate (f) from VV-2 or CV-2 (cfm) during purging based upon the whole body exposure limit is calculated by: 1.06 T [2.1(2)-171 (X/q) Ki Ci where: 1.06 = 500 mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit, whole body exposure 2.12E-3 = unit conversion factor= (60 sec/min x 3.53E-5 ft 3/cc)S Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.2.T Maximum value for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16).(3I24)(X/q)w The highest calculated short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mi 3) from ATTACHMENT M Table 2.3-36.'3.32E-4 sec/mi 3 (X/q)cv The highest calculated short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mi 3) from ATTACHMENT M Table 2.3-37.= 3.08E-4 sec/mi 3
- Procedure Number:.Beaver Valley Power Station Pr2-eureumer
______________________________1__ /2-ODC-2.02 Title: Unit: Level Of Use: 1_2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: ,I./, 2 ... ..26 of 130 : Ki The total whole body dose factor' due to gamma emissions from noble gas radionuclide 'T' (mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.C i The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.0 The flow rate (f) is also determined based upon the skin exposure limit as follows: 6.36 S T (X/q) (Li +l.IM)C 1 [2.1(2)-11.8]
where: 6.36 = 3000 mrem/yr x 2.12E-3 3000 mrem/yr = dose'rate limit, skin exposure 2.12E-3 = unit conversion factor= (60 sec/min x 3.53E-5 ft 3/cc)Li = The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-1I.Mi= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCi/m
- 3) from ATTACHMENT G Table(X/q) Same as above.* The flow rate (f) is determined by selecting the smaller of the calculated (f)values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
Procedure Number: Beaver Valley Power Station 1/2-oDC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 27 of 130 8.1.2.2.2 BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows: 0 The calculated monitor HIGH Alarm Setpoint above background (net uCi/cc) attributed to the noble gas radionuclides is determined by: f Ci Ei HSP F' [2.1(2)-19] F Eiave where: f The maximum acceptable containment purge flow rate (cfm) determined in Section 8.1.2.2.1. F' = The maximum actual or design effluent flow rate (cfm) at the point of release.53,700 cfm for VV-2 59,000 cfm for CV-2 Ci = The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.Ei = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b.Ei ave = The CR of equation [2; 1 (2)-6] divided by the sum of the Ci for the respective mix.NOTE: To enable maintaining a constant conversion factor from cpm to uCi/cc in the Digital Radiation Monitoring System software, the"calculated mix" is used rather than the analysis mix to calculate Ei ave above. This does not cause any change in the function of the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.* When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows: ASP = HSP x 0.5[2.1(2)-20] Beaver Valley Power Station Procedure Nu1b 2 er 2 0 2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 28 of 130 8.1.3 BV-1/2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determination. 8.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix For PV-1/2 Elevated Releases The calculated monitor count rate above background (CR), in ncpm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are shown in the following Table: BV-1/2 ALARM SETPOINTS FOR ELEVATED RELEASES cpm ABOVE BACKGROUND 60% SITE 30%(P)PRIMARY* LIMIT SITE MONITOR UPPER LIMIT (A)ALTERNATE ALARM LOWER MONITOR CR ALARM" Continuous Release (P)RM-1GW-108B 3.49E7 < 3.60E5 < 1.20E5.(A)RM-1GW-109(5) 2.61E7 < 3.60E5 < 1.20E5 '" Batch Release Of (P)RM-iGW-108B 3.93E5 < 2.36E5 < 1.18E5 BV-1 Decay Tanks or (A)RM-IGW-109(5) 7.87E6 < 3.60E5 1 1.20E5 BV-2 Storage Tanks*IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized: The setpoints were determined using a calculated mix from the FSAR and discharge flow rate of 1450 cfm for PV-1/2.The calculational method below was used to derive the monitor setpoints for the following operational conditions:
- Continuous release via PV- 1/2.* Batch release of BV-1 or BV-2 Waste Gas Decay Tank via PV-1/2.* Batch release of BV- 1 or BV-2 Containment Purge via PV- 1/2,is not shown in the above table. However, if it is necessary to perform a BV-1 or BV-2 Containment Purge via this release point, the alarm setpoint shall be calculated in accordance with Section 8.1.3.2.
Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 29 of 130 8'.1.3.1.1 BV-1/2 Mix Radionuclides The. "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows: " The gaseous source terms that are representative of the "mix" of the gaseous effluent were evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. The gaseous source terms can be obtained from ATTACHMENT A Tables 2.1-l a. and 2.1-lb.* The fraction cf the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was calculated by: ZAi Ai [2.1-9]where: Ai = The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la and 2.1.1b.8.1.3.1.2 BV-1/2 Maximum Acceptable Release Rate (Whole Body Exposure)The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limitwas determined by: Qt 500 [2.1.101 ZVi Si?, where: Vi The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrem/year/uCi/sec) from ATTACHMENT G Table 2.2-12.Si -From equation [2.1-9] Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: I 2 I 30 of 130 '8.1.3.1.3 BV-1/2 Maximum Acceptable Release Rate (Skin Exposure)Qt was also determined based upon the skin exposure limit as follows: 3000-[Li (X/Q)pv + 1.1B, ]S[where: Li = The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.(X/Q)pv The highest calculated annual average relative concentration of effluents releases via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) from ATTACHMENT F Table 2.2-6.-2.3 1E-6 sec/m 3 (0.5 -1.0 miles)(X/q)p, The highest calculated short term relative concentration of 'P effluents released via PV- 1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT N Table 2.3-38.= 1.07E-5 sec/m 3 (0.5 -1.0 miles)Bi = The constant for long term releases (greater than 500 hrs/year) for noble gas radionuclide "i"' accounting for the gamma radiation dose from the elevated finite plume (mrad/year/uCi/sec) from ATTACHMENT G Table 2.2-12.8.1.3.1.4 BV-1/2 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by: Qi = Si Qt [2.1-12]NOTE: Use the lower of the Qt values'obtained in Section 8.1.3.1.2 and 8.1.3.1.3.- Beaver Valley Power Station Procedure Numb 0 r:* 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:.. ..._*_2 31 of 130 8.1.3.1.5: BV-1/2 Maximum Acceptable Concentrations (Individual Radionuclide) The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide in the gaseous effluent was determined by: 2.12E -3 Qj Ci= F[2.1-13]where: 2.12E-3 = Unit conversion factor (60 sec/min x 3.53E-5 ft3/cc).F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.3.1.BV-1/2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide. (CR) was determined by: 8.1.3.1.6 CR= Ci Ei[2.1-14]where: Ei = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.8.1.3.1.7 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:* The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by: HHSP = 0.60 x CR[2.1-151* The monitor HIGH Alarm Setpoint above background (ncpm) was determined by: HSP = 0.30 x CR[2.1-16.] Procedure Number: Beaver Valley Power Station I I 1/2-ODC-2.02 Title: Unit: Level Of Use: In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: .2 32 of 1302 8.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release For PV-1/2 Elevated Releases The following calculation method applies to gaseous releases via the PV-1/2 Gaseous Waste/Process Vent when.the "calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the BV- 1/2 Gaseous Waste Gas Monitor (RM-GW-108B) or alternate (RM-1GW-109 CH 5) during the following operational conditions:
- Continuous release via PV-1/2.* Batch release of BV-1 or BV-2 Waste Gas Decay Tank via PV-1/2.* Batch release of BV-1 or BV-2 Containment Purge via PV-1/2.8.1.3.2.1 BV-1/2 Maximum Acceptable Release Rate Determine the maximurii acceptable discharge flow rate for the release from the Process Vent for the analyzed mix.0 The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by: 1.06S [2.1-211 f= XVi Ci where: 1.06 = 500mrem/yrx 2.12E-3 500 mrem/yr = dose rate limit, whole body exposure 2.12E-3 = unit conversion factor= (60 sec/min X 3.53E-5 ft 3/cc)S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.3.Vi = The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume (mrem/year/uCi/sec) from ATTACHMENT G Table 2.2-12.
Beaver Valley Power Station P r 2 erODC 2 O 2 Title: Unit: Level Of Use: 1/2 In-Field Reference. ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1_2 33 of 132 Ci The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas t6 be released., Based upon the skin exposure limit, (f) is calculated by: 6.36 S f= X [Li (X/Q)p, + 1.1 BIC 1 [2.1-22]where: 6.36 = 3000 mrem/yr x 2.12E-3 3000 mrem/yr = dose rate limit, skin exposure 2.,12E-3 = unit conversion factor= (60 sec/min x 3.53E-5 ft 3/cc)Li = The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCi/m
- 3) from ATTACHMENT G Table 2.2-11.(X/Q)pv The highest calculated annual average relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mr 3) from ATTACHMENT F Table 2.2-6.= 2.3 1E-6 sec/m 3 (X/q)p, = The highest calculated short term relative concentration of effluents released via PV- 1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/mi 3) from ATTACHMENT N Table 2.3-38.= 1.07E-5 sec/mr 3 Bi = The constant for long-term releases (greater than 500 hrs/year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/year/uCi/sec) from ATTACHMENT G Table 2.2-12.Select the smaller of the calculated f values based on the whole body exposure limit and based on the skin exposure limit shown above. The actual discharge flow rate (cfm) must be maintained at or below this (f) value.
Procedure Number: Beaver Valley Power Station 1o2eOmbe0,______________________________ 1/2-ODC-2.02. Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS RevisiOn: Page Number:.2 34 of 130 8.1.3.2.2 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows: 0 The calculated monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attributed to the noble gas radionuclides is determined by: f YXCi Ei HHSP F' [2.1-23]where: f = The maximum acceptable gaseous discharge flow rate (cfm)determined in Section 8.1.3.2.1. F' = The maximum actual or designr'effluent flow rate (cfm) at the point of release.= 1450 cfm for PV-1/2 Ci = The undiluted radioactivity of noble gas radionuclide "i" in the p gaseous source (uCi/cc) as determined by analysis of the gas to be released.Ei = The detection efficiency of the respective monitor (RM- 1GW- 108B)or (RM-IGW-109 CH 5) for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.When a HIGH-HIGH Alarm Setpoint has been calculated according to this section the monitor HIGH Alarm setpoint above background (ncpm) is determined by: HSP = HHSP x 0.5 [2.1-24]Iip Procedure Number: Beaver Valley Power Station 1/2-0 1 DC.2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 35 of 130 8.2 Compliance With 10 CFR 20 Dose Rate Limits (ODCM CONTROL 3.11.2.1)8.2.1 Dose Rate Due To Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents from the site is limited to 500 mrem/yr to the total body and 3,000 mrem/yr to the skin. Site gaseous effluents are the total of BV- 1 and BV-2 specific ground releases and a shared elevated release, the PV-1/2 Gaseous Waste/Process Vent. Based upon NUREG-0133 (3 1-3.1) the following equations are used to show compliance with ODCM CONTROL 3.1 1.2.1 .a.Ki +), Ki(X/Q) , Qj]< 500 mrem/yr [2.2-1][[Li(X-Q), + 1.1B,] Q, + [Li + 1.1M,] (X/Q), 1<3000 mrem/yr [2.2-2]where: K i The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrem/year/uCi/m 3.Li The skin dose factor due to beta emissions for each identified noble gas radionuclide "i", mrem/year/uCi/m 3.M i The air dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrad/year/uCi/m 3.Vi The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrem/year/uCi/sec. Bi The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume;mrad/year/uCi/sec. 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad. Qis, = The release rate of noble gas radionuclide "i" in gaseous effluents from free-standing stack, uCi/sec.Qi = The release rate of noble gas radionuclide "i' in gaseous effluents from all vent releases, uCi/sec.(X /Q )s = The highest calculated annual average relative concentration for any area at or'beyond the unrestricted area boundary for elevated releases (sec/m 3).(X / Q )v= The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/mi 3). Beaver Valley Power Station ProcedureNum:DC 2 2* .1/2-OC-.0 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: IPageNumber: 2 -36 of 130__2 At the Beaver Valley site gaseous releases may occur from the following Release Points (RP's) as shown in ATTACHMENT P Figure 2.4.2: RP 1 & 4. The BV-I Auxiliary Building Vent and the BV-2 SLCRS Unfiltered Pathway atop the Auxiliary Buildings (VV-1 and VV-2)RP 2 & 5. The BV-1 Rx Containment/SLCRS Vent and 'the BV-2 SLCRS Filtered Pathway atop the Containment Domes (CV- I and CV-2)RP 3. The BV-1/2 Gaseous Waste/Process Vent atop the BV-1 Cooling Tower (PV-1/2)RP 6. The BV-2 Condensate Polishing Building Vent (CB-2)RP 7. The BV-2 Waste Gas Storage Vault Vent (WV-2)RP 8. The BV-2 Decontamination Building Vent (DV-2)RP 9. The BV-2 Turbine Building Vent (TV-2)" The effluents from Release Point .1 & 4 are ground level in nature. At BV-1 the sources of these releases are Containment Purges and normal Auxiliary Building Ventilation. At BV-2 the sources of these releases are Containment Purges and Contiguous Area ventilation.
- Effluent from the Release Point 2 & 5 are assumed ground level in nature. At BV- 1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS). At BV-2 the source of these releases is normal Auxiliary Building Ventilation.
It is also possible to release Containment Purges from these vents." Release Points 6, 7, 8 and 9 are not normally radioactive release points." The effluent from Release Point. 3 are elevated, and the sources of these releases are the Main Condenser Air Ejectors, the Waste Gas Decay Tanks and the Containment Vacuum Pumps.Noble gas releases may normally occur from Release Points 1 through 5 above. To show compliance with the site limits of ODCM CONTROL 3.11.2.l.a, Equations [2.2-1] and [2.2-2] are expressed in terms of the actual release points for the site. Note that the expressions for release points 6, 7, 8 and 9 are included for use if radioactive releases via these release points are identified in the future. Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1_2 37 of 130 8.2.1.1 Total Body Dose Rate (All Release Points)* J. VQi + E i Ki [(X/Q)cv Qi + (X/Q)vv Qi +(I 1 11 CV1 VV I 1 p v .,c v l wv l Qi. + (X/Q)tv Qitv2 + (X/Q)cb Qi + (X/Q)dv Qi vv2 cb2_ 500 mrem/yr 8.2.1.2 Skin Dose Rate (All Release Points)X/Q)CV Qi + (X/Q) vv cv2+ (X/Q)wv Qi I dv2 wv2[2.2-3]2. Li,(X/Q)pv + .IB, Qi + + .i l.lM ][(X -Q cvQ i + (X/Q) Q +cv2 (X/Q)cv Qi + (X/Q)vv Qi + (X/Q)tv Qi + (X/Q)cb Qi + (X/Q)dv cv2 w2 tv2 cb2 Qi + (X/Q)wv Qi 3000 mrerrlyr [2.2-4]dv2 wv2 where: Qi pv iCvl Qi cv2 Qi lvv Qi tv2 Qi cb Qi dv2= Release rate of radionuclide "i" from the PV-1/2, uCi/sec.= Release rate of radionuclide "i" from CV-1, uCi/sec.= Release rate of radionuclide 'i" from CV-2, uCi/sec.= Release rate of radionuclide "i* from VV-1 Auxiliary Building, uCi/sec.= Release rate of radionuclide "i" from VV-2, uCi/sec.= Release rate of radionuclide "i" from TV-2, uCi/sec.= Release rate of radionuclide "i" from CB-2, uCi/sec.= Release rate of radionuclide "i" from DV-2, uCi/sec. Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 38 of 130 Qi Release rate of radionuclide "i" from WV-2, uCi/sec.wv2 (X/Q )p = Highest calculated annual average relative concentration for releases from the PV- 1/2, sec/m 3.(X/Q)CV = Highest calculated annual average relative concentration for releases from CV-1 and CV-2, Sec/m 3.(X/"Q)w Highest calculated annual average relative concentration for releases from VV-l and VV-2, sec/m 3.(X/Q )t, Highest calculated annual average relative concentration for releases for TV-2, sec/m 3.(X/Q )cb = Highest calculated annual average relative concentration for releases for CB-2, sec/m 3.(X/Q )dv = Highest calculated annual average relative concentration for releases for DV-2, sec/mr.(X/Q)wv Highest calculated annual average relative concentration for releases for WV-2, sec/m 3.The release rate for a containment purge is based on an averaged release rate in uCi/sec for the entire purge (not to exceed 960 min in accordance with ODCM CONTROL 3.11.2.1). All other terms remain the same as those defined previously. For the site, 4 potential modes of release are possible. The release modes identify the various combinations of sources of radioactivity and their release points which are used to determine the controlling locations. They are presented in ATTACHMENT C Table 2.2-1.For Release Modes 1, 2, and 3, the controlling location for implementation of ODCM CONTROL 3.11.2.1 .a is 0.35 miles NW. Inserting the appropriate X/Q's from ATTACHMENT F Tables 2.2-4 through 2.2-10 for this location, Equations [2.2-3] and[2.2-4] become: Procedure Number: Beaver Valley Power Station 1ou -om C-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2__39 of 132 8.2.1.3 Total Body Dose Rate (at 0.35 Miles NW).ZVQi i1 1+.Ki [9.24E-5Qi pv, 1 cv+ 1.03E -4Qi 11 v-v+ 9.24E -5 Q+2 cv 1.03E -4 Q+ 7.35E-5Q.+ 9.24E- 5 Qi dv+ 9.24E -5 Q 2 wv+2 2 Vv tv 7.35E-55 Q.-'cb2 1! 50Omremldyr [2.2-5]8.2.1.4 Skin Dose Rate (at 0.35 Miles NW)Z[7.OE-10L. +I.B1.IQi i YZ[Li +l.lMi]+9.24E-5Q. pv 1 cvl+1.03E-4 Q. + 9.24E -5 Q, lw 1+ 1.03E -4 Q.1+ 7.35E -5Q,+ 9.24E -5 Q.dv 2+9.24E -5 Q+ 7.35E -5 Qi ] < 3000 mrem/yr cb 2[2.2-6])For Release Mode 4, the controlling location is 0.75 miles N. Inserting the appropriate X/Q's from ATTACHMENT F Tables 2.2-4 through 2.2-10 for this location, Equations[2.2-3 and 2.2-4] become: 8.2.1.5 Total Body Dose Rate (at 0.75 Miles N)~V. Q. + EK4i 3.95E -6Q.I PV 1 i .Icv1+ 4.99E -6 Qi:+3.95E-6Q. 1+ 4.99E -6Q + 4.26E-6Qi 1 2 2 tv+3.95E-6Qi 2 dv+ 3.95E -6 Q i+ 4.26E -6 Q 2 cb I 2< 500 mrem/yr 8.2.1.6 Skin Dose Rate (at 0.75 Miles N)[2.2-7]Z [2.31E- 6 L +,1.1Bi]Qi ii+ f [Li + .lMi ][3.5E-6Qi pv 1 I cv+4.99E-6Qi I vv+3.95E-6Qi+ 4.99E-6Q i+ 4.26E-6Q i 2 tv+ 3.95E-6Qi dv+ 3.95E-2 2 9 cv vv 6 Q + 4.26E -6 Qi] < 3000 mrem/yr[2.2-8]WV cb Procedure Number: Beaver Valley Power Station Proedureumber: _ _ _ _ _ _ _ _ _ _ _ .1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: PageNumber: 2 40 of 13-0___.8.2.1.7, Determination of Controlling Location, The determination of controlling location for implementation of ODCM CONTROL 3.11.2.1 .a for noble gases is a function of the following parameters: " Radionuclide mix and their isotopic release rate* Release Mode" Meteorology The incorporation of these 3 parameters into Equations: [2.2-31 and [2.2-4] resulted in the equations for the controlling locations as presented in Equations [2.2-5'through 2.2-8].The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GAS IBB (similar to NUREG-0017.(3'1 3 4) Inputs were based on operating modes of the respective plants. The code inputs utilized are presented in 1/2-ODC-3.01. The source term is presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point. )The X/Q values utilized in the equations for implementation of ODCM CONTROL 3.11.2.1 .a are based upon the maximum long-term annual average X/Q in the unrestricted area. ATTACHMENT E Table 2.2-3 presents the distances from the Release Points to the nearest unrestricted area for each of the 16 sectors as well as to the nearest vegetable garden, cow, goat, and beef animal. ATTACHMENT F Tables 2.2-4 through 2.2-10 present the long-term annual average (X/Q) values for all Release Points to the special locations presented in ATTACHMENT E Table 2.2-3.A description of their derivation is provided in 1/2-ODC-3.01. For Release Modes 1, 2, and 3, dose calculations were performed using the highest calculated site boundary X/Q values applicable to the release points involved and the projected radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release could contribute to the dose at a given location, the selection of the two highest sector X/Q values at the site boundary considered this contribution. From these results, the distance.and sector associated with the highest, calculated site boundary dose were selected as the controlling location.For Release Modes 1, 2, and 3 the controlling location is 0.35 miles NW. In Release Mode 1, the dominant release is via VV-1 and CV-2. In Release Modes 2 and 3, the dominant release is a Containment Purge from the VV-1 or VV-2.K) Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 41 of 130 For Release Mode 4, a similar evaluation was performed. Long-term annual average X/Q values were calculated at the mid-point of the 10 standard distances listed in ATTACHMENT F Table 2.2-4 through 2.2-10. In that a simultaneous, ground level release could contribute to the dose at a given location, the selection of the two highest X/Q values at the controlling distance considered this contribution. Since the two maximum X/Q values occurred in the 0.5 -1.0 mile radial band, the controlling distance was selected at 0.75 miles. From the calculated dose results, the controlling sector was shown to be North. In this Release Mode, the dominant release is a Containment Purge via the PV- 1/2 Gaseous'Waste/Process Vent. Neither of the controlling receptor locations are presently inhabited. Values for Ki, Li, and Mi, which were used in the determination of the controlling receptor location and which are to be used in Equations [2.2-5] through [2.2-8] to show compliance with ODCM CONTROL 3.11.2.1.2, are presented in Table 2.2-11.Values taken from Table B- 1 of NRC Regulatory Guide 1.109, Revision 1,(3.1.3.5) were multiplied by 1 E6 to convert picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.Values for Vi and Bi for the finite plume model can be expressed as shown in Equation [2.2-9] and [2.2-10]. Values were calculated using the NRC code RABFIN at the site boundary location which would receive the highest total dose from all Release Points. These values are presented in ATTACHMENT G Table 2.2-12 and calculated from the following equation: B =Kk Ali Ua El [2.2-9]rd jk1 uj where: I = The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (uj) and atmospheric stability class "k" for a particular wind direction. K = A numerical constant representing unit conversions. (260 mrad)(radians) (m 3) (transformation) 16 sectors 1 (sec)(Mev)(Ci) 12n radians ]1E-6 Ci 3.15E7 sec]uCi2 [a yrM_2. 1E4 mrad (m 3) (transformation)/yr(Mev)(uCi). rd = The distance from the release point to the receptor location, meters. Procedure Number: Beaver Valley Power Station 1/oe °eN2ber_______________________________________ 1/2-ODC-2.02 Title: Unit: Level Of Use: In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 42 of 130 ".uj= The mean wind speed assigned to the "j" th wind speed, class, meters/sec. fik The joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless). Ali The number of photons of energy corresponding to the "I" th energy group emitted per transformation of the "i" th radionuclide, number/transformation. El= The energy'assigned to the "1" th energy group, Mev.Ua = The energy absorption coefficient'in air for photon energy HI, meters The Vi factor is computed with conversion from air dose to tissue depth dose, thus: K f A u ElI -uTT V =I.IK z jk .i a d [2.2-10]i rdjklu d jJ where: uT The tissue energy absorption coefficient for photons of energy El, cm 2/gm.Td = The tissue density thickness taken to represent the total body dose (5gm/cm 2).1.1 The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad. 8.2.2 Dose Rate Due To Radioiodines And Particulates The dose rate in unrestricted areas resulting from the of inhalation of 1- 131, tritium, and all radionuclides in particulate form (excluding C- 14) with half lives greater than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem/yr to any organ.Based upon NUREG-0133,(3".. the following basic equation is used to show compliance with ODCM CONTROL 3.11.2.1 .b:[(X/Q)s Qis +(X/Q)" Qiv] -1,500 mrem/yr [2.2-11]where: Pi, = Dose parameter for any organ t for'each identified radionuclide "i", mrem/yr per uCi/m3.Qi = The release rate of radionuclide "i", in gaseous effluents from elevated releases, uCi/sec. Beaver Valley Power Station Procedure Numbor: 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 43 of 130 Qiv The release rate of radionuclide "i", in gaseous effluents from ground level releases, uCi/sec.(X/Q), = The highest calculated annual average relative concentration at the unrestricted area boundary for elevated releases, sec/m 3.(X/Q) = The highest calculated annual average relative concentration at the unrestricted area boundary for ground level releases, sec/m 3.NOTE: !The dispersion parameters specified in Section 8.2.2 are limited to the site boundary as defined above.Releases may occur from any Release Point in the Release Modes listed in ATTACHMENT C Table 2.2-1. To show compliance with ODCM CONTROL 3.11.2.1 .b, Equation [2.2-11] is now expressed in terms of the actual Release Points for the site.Pi [(X/Q)pv Qi I T p pv+ (XQ~c Qicv'+ (X/Q)vv Qi vv,+ (X/Q)cv Q Ki + (X/Q) vv] < 1500 mrem/y (X/Q)tv Qi tv 1+ (X/Q)cb Qicb'+ (X/Q)dv Qidv2+ (X/Q)v Qi wv2[2.2-12]where: (X/Q)pv Highest calculated annual average relative concentration for releases from PV-1/2, sec/m 3.(X/Q)c = Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m 3.(X/Q) = Highest calculated annual average relative concentration for releases from VV-1 and VV-2, sec/M 3.(X/Q), = Highest calculated annual average relative concentration for releases 3 from TV-2, sec/mr.(X/Q)Cb = Highest calculated annual average relative concentration for releases from CB-2, sec/m 3. Beaver Valley Power Station Procedure Number: B r e wa1/2-ODC-2.02 Title: Unit: Level Of Use: 112 ~In-Field Reference .1 ODCM: GASEOUS EFFLUENTS Revision: Page Number: _OD M: G SE USE FL EN S2 44 of 130 (X/Q)dV = Highest calculated annual average relative concentration for releases from DV-2, sec/m 3.= Highest calculated annual average relative concentration for release from WV-2, sec/m 3.Qi = Long-term release rate of radionuclide "'T from PV-1/2, uCi/sec.pv Qi Long-term release rate of radionuclide "i" from CV-1, uCi/sec.cvl Qi Long-term release rate of radionuclide "i"j from CV-2, uCi/sec.1v2 Qi Long-term release rate of radionuclide "i" from VV-1, uCi/sec.1vv L Qi2 Long-term release rate of radionuclide "i" from VV-2, uCi/sec.Qib2 = Long-term release rate of radionuclide "i" from TV-2, uCi/sec.Qidv2 Long-term release rate of radionuclide 'T' from DV-2, uCi/sec.Qi = Long-term release rate of radionuclide "i" from CV-2, uCi/sec.1 dv2 Qi Long-term release rate of radionuclide. "i" from WV-2, uCi/sec.wv2 All other terms are the same as those defined previously. TV-2, CB-2, DV-2 and WV-2 are not normal radioactive Release Points. These Release Points are included only for use if radioactive releases via these vents are identified in the future. In the calculation to show compliance with ODCM CONTROL 3.11.2.1 .b only the inhalation pathway is considered. Values of the organ dose parameters, Pi, were calculated using methodology given in NUREG-0133.(3'3') For the child age group, the following equation was used for all nuclides. The Pi, values are presented in ATTACHMENT H Table 2.2-13.Pi, = 3.79E9 DFAi, [2.2-13] Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title. Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:_2 45 of 130 where: 3.7E9 = Breathing rate of child (3,700 m 3/yr) x unit conversion factor (1E6 pCi/uCi).DFAiT = The organ inhalation dose factor for a child from Table 6 of NUREG-0172,(3"'36) for organ t, nuclide "i", in units of mrem/pCi.For Release Modes 1 through 4, the controlling location is the site boundary, 0.35 miles NW.Equation [2.2-12] becomes:.PiT [7.OOE -10 Qi 1 9.24E- 5Q +-cv2+ 9.24E -5 Q.acvl+ 1.03E -4 Q.i + 7.35E -5 Q +VVl 'tvl pv 1.03E -4 Qi+ 7.35E- 5 Qitv2 + 7.35E -5 Qicb2 + 9.24E -vv2 5Q. + 9.24E-5.Qi ] -1500 mrem/yr 1 dv2 1 i2 8.2.2.1 Determination of Controlline Location[2.2-14]The determination of the controlling location for implementation of ODCM CONTROL 3.11.2.1 .b for radioiodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Equation [2.2-12] results in the respective equations for each Release Mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.In the determination of the controlling site boundary for eachRelease Mode, the highest 2 site boundary X/Q values for each Release Point were utilized in conjunction with the radionuclide mix and the release rate for each Release Point to determine the controlling location.The Pi, values are presented in ATTACHMENT H Table 2.2-13.The X/Q values in Equation [2.2-14] were obtained from ATTACHMENT F Tables 2.2-4 through 2.2-10.A description of the derivation of the X/Q values is provided in 1/2-ODC-3.01. Procedure Number: Beaver Valley Power Station 1o2r ODC-2o"2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 46 of 1302 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)(Gaseous)At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radwaste system. The effluent from both units are mixed and discharged from a common Release Point, the PV-1/2 Gaseous Waste/Process Vent, at the top of the Unit 1 Cooling Tower'.The resulting dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception would be a Containment Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5.8.3.1 Dose Due To Noble Gases 8.3.1.1 Cumulation Of Doses Section II.B. 1 of Appendix I of 10 CFR 50 (ODCM CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. In addition, ODCM CONTROL 3.11.2.4 requires use of radwaste system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta. p Based upon NUREG-0133, 3(31) the air dose limits in the unrestricted area due to noble gases released in gaseous effluents are defined by the following equations: 8.3.1.1.1 Gamma Radiation Quarter Limit 3.17E-8Z[M [(X/Q)vQ. +1(Xqq)vqv] +[BiQis +biqisj 5mrad [2.3-1]8.3.1.1.2 Beta Radiation Quarter Limit 3.17E-8 8 Ni. [(X/Q)vQiv +(X/q)vqiv + (X/Q)sQi +(tqq)sqiS)]< 10mrad [2.3-2]sii 8.3.1.1.3 Gamma Radiation Year Limit 3.17E-8 Y. [Mi[(X/Q)v Qiv+(X/q)vqiv] +[BiQis +biqis]]5 10mrad 8.3.1.1.4 Beta Radiation Year Limit 3.17E-8 8 N [(X/Q)vQ + (X/q) qiv + (X/Q) Qi + (X/q) qis 20 mrad ___v3iv v4 s is s-i[2.3-4] ) Beaver Valley Power Station Procedure Number: 1/2-ODC-2.02 Title: Unit: Level Of Use: e* 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 47 of 130 8.3.1.1.5 Gamma Radiation Projection Averaged Over 31 Days 3.17E-8Y[MIi 1(X/Q)vQiv +(X/q)vqivJ+ [BiQis +b iqisj < 0.2 mrad [2.3-5]i 8.3.1.1.6 Beta Radiation Projection Averaged Over 31 Days 3.17E -8 E Ni [(-X/Q) v Qiv + (X/q)v qiv + (X/Q)s Qis + (X/q)s qisj-- 0.4 mrad [2.3-6]i where: Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3).Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3).(X/Q), = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases greater than 500 hrs/year (sec/m 3).(X/q), The relative concentration for areas at or beyond'the unrestricted area boundary for short-term vent releases equal to or less than 500 hrs/year (sec/mr 3).(X/Q)S = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack releases greater than 500 hrs/year (sec/mr 3).(X/q), = The relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases equal to or less. than 500 hrs/year (sec/m 3).qis = Release of noble gas radionuclide "i" in gaseous effluents for short-term stack releases equal to or less than 500 hrs/year (uCi).qiv Release of noble gas radionuclide "i" in gaseous effluents for short-term vent releases equal to or less than 500 hrs/year (uCi).Qis Release of noble gas radionuclide "i" in gaseous effluents for long-term free standing stack releases greater than 500 hrs/year (uCi).Qiv = Release of noble gas radionuclide "i" in gaseous effluents for long-term vent releases greater than 500 hrs/year (uCi). Procedure Number: Beaver Valley Power Station i 1/2 -ODC-2.02 Title: ]Unit: [Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: I ~~~2 I 48 of 130 B i The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).bi = The constant for short-term releases (equal to or less than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).3.17E-8 The inverse of the number of seconds in a year.NUREG 0133(3..31) permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions. This special consideration is applied in Equations [2.3-1] through[2.3-6], however, a summary of the "real time" meteorological data coupled with the corresponding releases shall be included in the Annual Radioactive Effluent Release Report.Short-term releases are also evaluated annually in computer codes technically consistent with XOQDOQ and GASPAR for inclusion in the Annual Radiological Environmental Report.The incorporation of this option and the Release Modes of ATTACHMENT I Table 2.3-1 results in the following equations to show compliance with 10 CFR 50 for the calendar quarter or year.8.3.1.1.7 Gamma Radiation Dose Equation 3.17E-8Y[Mi [(X/Q)cvQi +(X/Q) vvQi + (X/Q)cbQi +(X/Q)dvQi +1 cv vv cb dv (X/Q) Qi ]+0.5BiQi ] [2.3-7]wv [2.Wv P< 0.2 mrad (per 31 days), or< 5.0 mrad (per quarter), or<10.0 mrad (per year). Beaver°Valey Power Station -Procedure Number:,..~..1/2.ODC-2.02 Title: B V Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision' Page Number: ,2 49 of 130 8.3.1.1.8 Beta Radiation Dose Equation 3.17E-8 YX N.i[(X/Q)cvQi. +(X/Q)vvQi. + (X/Q)cbQ V 1cv cb (X/Q)w Qi + 0.5 (X/Q)pv Qipv ]Wv< 0.4 mrad (per 31 days), or.; 10.0 mrad (per quarter), or< 20.0 mrad (per year)where: (X/Q),cv = Annual average relative concentration for releases f (sec/m 3).(X/Q) = Annual average relative concentration for releases f (sec/mr 3).(X/Q)pv = Annual average relative concentration for releases f (X/Q) , = Annual average relative concentration for releases f Qi = Release of radionuclide "i" from CV-1 and CV-2 (u cv Qi = Release or radionuclide 'i" from VV-I and VV-2 (u Vv Qi = Release of radionuclide "i" from PV-1/2 (uCi).pv Qi = Release of radionuclide 'T' from TV-2 (uCi).tv Qi = Release of radionuclide "'" from the CB-2 (uCi).6b Qi = Release of radionuclide ."i" from, DV72 (uCi).dv Qi = Release of radionuclide "i" from WV-2 (uCi).WV+ (X/Q)dvQi +dv[2.3-8]rom CV- I and CV-2 rom VV-1 and VV-2 rom PV-1/2 (sec/m 3).rom TV-2 (sec/mr 3).Ci).tCi). Procedure Numbeer: Beaver Valley Power Station 1/2-ODC-2.02 Title: "'Unit: ... Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: .S2 ý:" "5 of 130 " .For Release Modes 1, 2, 3, and 4 the controlling location is 0.35: miles NW. Substitution of the appropriate X/Q values into Equations [2.3-7] and [2.3--8] results in the following: 8.3.1.1.9 Gamma Radiation Dose Determination 3.17E-8Yi[Mi[9.24E-5Qi +l.03E-4Qi +7.35E-5Q. +7.35E-5Q. +i cv vv lv cb 9.24E -5 Q +9.24E-5Qi ]+0.5BiQi [2.3-9]dv Wv pv< 0.2 mrad (per 31 days), or< 5.0 mrad (per quarter), or< 10.0 mrad (per year)8.3.1.1.10 Beta Radiation Dose Determination +1.03E-4Qi +7.35E-5Qi +7.35E-5Qi +1 cv vv tv cb 9.24E-5Qi +9.24E-5Qi +(0.5)7.OE-1OQi ] [2.3-10]dv wv pv)< 0.4 mrad (per 31 days), or< 10.0 mrad (per quarter), or< 20.0 mrad (per year)8.3.1.1.11 Determination of Controlling Location The determination of the controlling locations for implementation of 10 CFR 50 is a function of the following parameters:
- Radionuclide mix and their isotopic release* Release Mode* Meteorology The incorporation of these parameters into Equations
[2.3-7] and [2.3-8]resulted in the equations for the controlling locations as presented in Equations[2.3-9] and [2.3-10]. The radionuclide mix was based upon source terms calculated using the NRC'GALE Code (gee 1/2-ODC-3.01 for inputs) and are shown in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.I" Beaver Valley Power Station Procedure NumbeDC 2 0 2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 51 of 130 As in Section 8.2.1, for each Release Mode, the two highest boundary X/Q values for each release point and release duration were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since elevated releases occur from the BVPS site and their maximum X/Q values may not decrease with distance (i.e., the site boundary may not have highest X/Q values), the two highest X/Q values for those distances, greater than the site boundary, were also considered in conjunction with the radionuclide mix to determine the controlling location.These values of X/Q were obtained for the midpoint of the 10 standard distance intervals previously presented in ATTACHMENT F Tables 2.2-4 through 2.2-10.For each Release Mode, a particular combination of Release Point mix and meteorology dominates in the determination of the controlling location. For Release Modes 1, 2, 3, and 4 the controlling release is VV-1 and VV-2. For Release Mode 3, the controlling release is CV-I and CV-2.Values for Mi and Ni, which were used in the determination of the controlling location and which are to be used by BV-l and BV-2 in Equations [2.3-9] and[2.3-10] to show compliance with 10 CFR 50 were presented in ATTACHMENT G Table 2.2-11. Values taken from Table B-I of Regulatory Guide 1.109, Revision 1(.1-3.1 5) were multiplied by 1 E6 to convert from picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.In determination of the controlling location for Release Modes 1, 2, 3, and 4, ATTACHMENT F Tables 2.2-4 through 2.2-7 are utilized for X/Q values. The Bi values to be utilized are the same values which were presented in ATTACHMENT G Table 2.2-12. A description of the derivation of the various X/Q values is presented in 1/2-ODC-3.01. The following relationship must hold for BV- 1 or BV-2 to show compliance with ODCM CONTROL 3.11.2.2: For The Calendar Quarter D7 < 5.0 mrad [2.3-11]Dp < 10 mrad [2.3-12]For The Calendar Year D7< 10 mrad [2.3-13]Do < 20 mrad[2.3-14] Procedure Number: Beaver Valley Power Station /2-ODC-2.02 Title: Unit Level Of Use:In-Field Reference ODCM: GASEOUS EFFLUENTS IRevision: Page Number:_ _ _ _2 ____52_of 2130 .-where: D = The air dose from gamma radiation (mrad).D = The air dose from beta radiation (mrad).The quarterly limits given above represent one-half the annual design objective of Section II.B.1 'of Appendix I of 10 CFR 50. If any of the limits of Equations[2.3-11] through [2.3-14] are exceeded, a special report pursuant to both Section IV.A' of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations. In addition, ODCM CONTROL 3.1.2.4 requires that the gaseous radwaste system must be used to reduce radioactive materials in that waste when projected doses from each reactor unit when averaged over 31 days exceed any of the following: Dy < 0.2 mrad [2.3-15]Do < 0.4 mrad [2.3-16]8.3.1.2 Projection Of Doses (Noble Gas) )Doses due to gaseous releases from BV-1 and BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.2.2 Proiection Of Doses for additional specifications). The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.(Also see Section 8.3.2.2 Projection Of Doses for additional specifications). The doses used in the 31-day dose projection will be calculated using Equations [2.3-9]and [2.3-10] as appropriate. The 31-day dose projection shall be performed according to the following equations: 8.3.1.2.1 When Including Pre-Release Data, D [ _Bj (3 1)+C [2.3-17]T3 ...Beaver Valley Power Station ProcedureNui-ObDC.2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 53 of 130 8.3.1.2.2 When Not Including Pre-Release Data, D 3 1 T (31)+C [2.3-18]where:.D 3 1 = Projected 31 day dose (mrad).-A = Cumulative dose for quarter (mrad).B = Projected dose from this release (mrad).T = Current days into quarter.C = Value which may be used to anticipate plant trends (mrad).8.3.2 Dose Due To Radioiodines And Particulates 8.3.2.1 Cumulation Of Doses Section I1.C of Appendix I of 10 CFR 50 (ODCM CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radioiodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition, ODCM CONTROL 3.11.2.4 requires the use of gaseous radwaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon NUREG-0133 ,(3I3l) the dose to an organ of an individual from radioiodines and particulates, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following equation: 8.3.2.1.1 Radioiodines and Particulates Month, Quarter, and Year Limits 3.17E-8 .ZRi [W Qi + wsqis + WvQiv + wvqiv]1 I S v v< 0.3 mrem (per 31 days), or [2.3-19]< 7.5 mrem (per quarter), or_ 15.0. mrem (per calendar year) .Procedure Number: .Beaver Valley Power Station Pr ,__1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:~2 54 of 1 30 where: Qis = Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs/yr (uCi).Qi = Release of radionuclide 'T? for long-term vent releases greater than 500 hrs/yr (uCi).qis Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs/yr (uCi).qiv = Release of radionuclide "i" for short-term vent releases equal to or less than 500 hrs/yr (uCi).ws = Dispersion parameter for estimating dose to an individual at the controlling location for long-term free standing stack releases greater than 500 hrs/yr.sec/m 3 for the inhalation pathway, ( W/Q )s.meters 2 for the food and ground plane pathway, (D/Q )s.W = The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs/yr.sec/m 3 for the inhalation pathway, (X/Q )v.meters" 2 for the food and ground plane pathway, (D/Q )v.Ws Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases equal to or less than 500 hrs/yr.= sec/mr 3.for the inhalation pathway, (W/q )s.= meters" 2 for the food and ground plane pathway, (D/q)s.Wv The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases equal to or less than 500 hrs/yr.= sec/m 3 for the inhalation pathway, (X/q)v.= meters" 2 for the food and ground plane pathway, (D/q )v. Proedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 55 of 130 3.17E-8 = The inverse of the number of seconds in a year.Ri., The dose factor for each identified radionuclide "i" for the organ "1'" of interest (mrem/yr per uCi/sec per m-2 or mrem/yr per uCi/m 3).Radionuclides and particulates may be released from any of the BV- 1 and BV-2 Release Points in the Release Modes identified in ATTACHMENT I Table 2.3-1. As described previously in Section 8.3.1.1, NUREG 0133(3.'1.1) permits use of long-term annual average dispersion calculations (which with the release modes of Table 2.3-1 results in the following equations) to show compliance with ODCM.CONTRQLS 3.11.2.3 and 3.11.2.4. For a particular organ, Equation [2.3-19] becomes: 8.3.2.1.2 Radioiodines and Particulates Dose Equation 3.17E-8 [0.5W pvQi + WcvQi + WvvQi + W tvQi +W cbQi +,v 1pv cv w tv cb WdvQi +Wwv Qi ] [2.3-20]dv wv< 0.3 mrem (per 31 days), or< 7.5 mrem (per quarter), or< 15.0 mrem (per calendar year)where: 0.5 Wpv ' Dispersion parameter for releases from PV-1/2. The value of 0.5 represents the portion of dose assigned to each Unit due to this being a shared Release Point WCv Dispersion parameter for releases from CV-1 and CV-2.Ww =Dispersion parameter for releases from VV-1 and VV-2.Wtv =Dispersion parameter for releases from TV-2.Web Dispersion parameter for releases from CB-2.Wdv = Dispersion parameter for releases from DV-2.Wwv = Dispersion parameter for releases from WV-2.Qi Release of radionuclide "i" from PV-1/2 (uCi).v Pv BeaverTT 11 __ Proedure Numiber: ..Beaver Valley Power Station :1/2-ODC 2 0 2 Title: Unit: Level Of Use:/2 In-Field Reference o ODCM: GASEOUS EFFLUENTS Revision: Page Number 2 56 of 130 .Qi = Release of radionuclide "i" from CV-l and CV-2 (uCi)..Cv Qi = Release of radionuclide "i" from VV-1 and VV-2 (uCi).vv Qi Release of radionuclide "i" from TV-2 (uCi).tv Q, Release of radionuclide 'i7 from CB-2 (uCi).eb Qi = Release of radionuclide "i" from DV-2 (uCi).dv Qi = Release of radionuclide "i" from WV-2 (uCi).Wv TV-2, CB-2, DV-2 and WV-2 are not normally radioactive Release Points.These are included only" for use if a radioactive release is identified in the future.In determining the dose at a particular location, dispersion parameter W is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q.Incorporation of the various pathways into Equation [2.3-20] results in the following equation for a particular organ: 8.3.2.1.2.1 Radioiodines and Particulates Dose Determination 3.17E-8 Z[[R. -+R. -R. +R. ][0.5W Qi +W Qi +-i TG I, 1 I'v 1 BCv WwQi.+ WtvQi.v + WcbQic. + W dvQ. + W vQi. ]vv tv 1 N cb 1 cb dv i W+ R.rcx [0.5(X/Q) pvQpv + (X/Q) cvQicv +(X/Q) QiW +(X/Q)tQ i +(X/Q)bQi + (X/Q)dQ +(XIQ)tvicbi + X dv i wv tv cb dv QiWv ] [2.3-21]< 0.3 mrem (per 31 days), or .)< 7.5 mrem (per quarter), or< 15.0 mrem (per year) Beaver Valley Power Station Proedre ,, ODC 2 2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 57 of 130 where: R. = Dose factor for an organ "-r" for radionuclide "i" for the ground ITG plane exposure pathway (mrem/yr per uCi/sec per m-2).R. = Dose factor for an organ "`" for radionuclide 'T' for either the 11M cow milk or goat milk pathway (mrem/yr per uCi/sec per m2).R. = Dose factor for an organ "r" for radionuclide "i" for the vegetable pathway (mrem/yr per uCi/sec per m-2).R ... B = Dose factor for an organ "T" for radionuclide "j" for the meat pathway (mrem/yr per uCi/sec per m-2 R. = Dose factor for an organ ",r" for radionuclide "i" for the IT I inhalation pathway (mrem/yr per uCi/m 3).It should be noted that WPV, Wcv, Ww, WW, WC,, Wdv, and Wwv in Equation[2.3-21] are in terms of D/Q(m2).Values of the dose factor, were calculated using the methodology of NUREG-0133.(3.1. 3 , 1) The following equations were used for all nuclides except tritium: Dose Factors For Inhalation Pathway R. = K' (BR)a(DFAii)a IT'I 8.3.2.1.2.2 = mrem/yr per uCi/m 3[2.3-22]Where: K'(BR)a (DFAi,)a= A constant of unit conversion (1E6 pCi/uCi).= The breathing rate of the receptor of age group "a" (m 3/yr).= Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem/pCi). Inhalation dose factors (DFAit) by organ for the various age groups are given in Table E-7 through E- 10 of Regulatory Guide 1.109, Rev. 1(31"3*5) or Tables 5 through 8 of NUREG-0172.(' -.3.6) Beaver Valley Power Station Procedure Numbr:/ODC 2 2 Title: Unit: 1/2 Level Of Use: In-Field Reference I/ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 1 ' rNR rfl21 J The breathing rates (BR)a used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109.(31'-'-) Age Group(a) Breathing Rate (m 3/yr)Infant Child Teen Adult 1400 3700 8000 8000 8.3.2.1.2.3 Dose Factors For Ground Plane Pathway R.ITG= K'K" (SF)DFGi,[(1 -e"i t)/?,i]= m 2-mrem/yr per uCi/sec[2.3-23]where: 'p K' A constant of unit conversion (1 E6 pCi/uCi).K" = A constant of unit conversion (8760 hr/year).Xi = The decay constant for the "i" th radionuclide (sec't).t = The exposure time (4.73E8 sec or 15 years).DFGiT = The groundplane dose conversion factor for organ "r" for the "i" th'radionuclide (mrem/hr per pCi/rn 2). A tabulation of DFGi, values is presented in Table E-6 of Regulatory Guide 1.109.(3.1.3.5) SF = The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used. (3.1.3.5)I..9 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:.... ...2 59 of 130:8.3.2.1.2.4 Dose Factors For Cow Milk or Goat Milk Pathway R.U =pl K+___ (I- f~fs,ýith]-L RiTM KQF(UaP)Fmr(DL)fPfs + -f y j- thI-i t f(r)(DFLO,) +s e ki + X" KPY-m 2 -mrem/yr per uCi/sec [2.3-24]where: K' A constant of unit conversion (1 E6 pCi/uCi).QF = The animal's consumption rate, wet weight (kg/day).Uap = The receptor's milk consumption rate, for age "a" (liters/yr). YD = The agricultural productivity by unit area of pasture feed grass (kg/m2).Ys = The agricultural productivity by unit area of stored feed (kg/m2).Fm = The stable element transfer coefficients (days/liter). r = Fraction of deposited activity retained on animals feed grass.(DFLi,)a = The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem/pCi). Ingestion dose factors (DFLi,)a for the various age groups are given in Table E- 11 through E-14 of Regulatory Guide 1.109('-.'.5 or Tables I through 4 ofNUREG-0172.(3'3 6)Xi The decay constant for the "i" th radionuclide (sec-1).%w The decay constant for removal of activity on leaf and plant surfaces by weathering 5.73E-7 sec-' (corresponding to a 14 day half-life). tf The transport time from pasture, to animal, to milk, to receptor (sec).th The transport time from pasture, to harvest, to animal, to milk, to receptor (sec).fP= Fraction of the year that the animal is on pasture (dimensionless). BP Procedure Number 0 .Beaver Valley Power Station I .1/2-ODC-O2.02 Title: ODCM: GASEOUS EFFLUENTS Unit: Level Of Use: 1/2 1 In-Field Reference Revision: jPage Number:.2 I 60 of 130-M 1.I ............. a¢Fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless). Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.1 09.(3'5)Parameter r (dimensionless) F. (days/liter) Uap (liters/yr) -infant child teen adult (DLFi,)a (mrem/pCi) YP (kg/m 2)Ys (kg/m 2)tf (seconds)th (seconds)QF (kg/day)Value 1.0 for radioiodine 0.2 for particulates each stable element 330 330 400 310 each radionuclide 0.7 2.0 1.73E5 (2 days)7.78E6 (90 days)50 0.5 1.0 RG. 1.109 Table E-15 E-15 E-1 (cow milk)E-2 (goat milk)E-5 E-5 E-5 E-5 E-11 to E-14 E-15 E- 15 E-15 E-15 E-3 I -ýfl For goat's milk, all values remain the same except for QF, which is 6 kg/day.I. Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 61 of 130 8.3.2.1.2.5 Dose Factors 'For Meat Pathway R =-K, QF(Uap) fpfs I(- fpfs)e-)ithl _?,itf Ri Kr F, F(r)(DFLia P -+ e -It IT. +~ f ITa y J m 2 -mrem/yr per uCi/sec [2.3-251 where: Ff =The stable element transfer coefficients (days/kg). Uap = The receptor's meat consumption rate for age "a" (kg/yr).tf = The average time from slaughter of meat animal to consumption (sec).th = The transport time from crop field to receptor (sec).All parameter values are the same as the milk pathway parameter values except Ff which is obtained from Table E- 1. Parameter tf is obtained from Table E- 15, and Uap is obtained from Table E-5. These values, as obtained from Regulatory Guide 1. 109,(3-.3.') are as follows: Parameter Value RG- 1.109 Table Ff (days/kg) each stable element E- 1 tf (seconds) I1.73E6 (20 days) E-15 U (kg/yr) -infant 0 E-5 Child 41 E-5 Teen 65 E-5 Adult 110 E-5 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore: Beaver Vall Pw Procedure Number:V H PI ver e Powe Saion 17 , /200720 Title: ODCM: GASEOUS EFFLUENTS Unit: Level Of Use: 1/2 In-Field Reference Revision: Page Number: 2 62 of 130 8.3.2.1.2.6 Dose Factors For Vezetation Pathway Riv K' X (r)+ 1 L (DFLi)a[ULfe -itL + USf e -'ith]= m 2-mrem/yr per uCi/secý.3-26]where: K' = A constant of unit conversion (1E6 pCi/uCi).L = The consumption rate of fresh leafy vegetation by the receptor in age Ua cosmto=ef eeainb group "a" (kg/yr).us The consumption rate of stored vegetation by the receptor in age group"a" (kg/yr).fL = The fraction of the annual intake of fresh leafy vegetation grown locally.fg = The fraction of the annual intake of stored vegetation grown locally.tL = The average time between harvest of leafy vegetation and its consumption (seconds). th = The average time between harvest of stored vegetation and its consumption (seconds). Yv= The vegetation area density (kg/m 2).all other factors are defined previously. Beaver Valley Power Station P /-ocoduD2Number: " , ....1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS -Revision: Page Number: 1 2 63 of 130 Tabulated below are the appropriate parameter Values and their reference to Regulatory Guide 1.109.(3.135) Parameter r (dimensionless)(DFLi,)a (mrem/pCi) U L (kg/yr) -infant a Child teen adult U a(kg/yr) -infant.child teen adult fL (dimensionless) Value 1.0 for radioiodines 0.2 for particulates each stable element RG- 1.109 Table E-15 E-15 E-11 to E-14 0 26 42 64 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 0 520 630 520 1.0 Fg (dimensionless) 0.76 tL (seconds)th (seconds)Yv (kg/m2)8.6E4 (1 day)5.18E6 (60 days)2.0 E-15 E-15 E-15 E- 15 E-15 As discussed in Section 8.2.2 for tritium, the parameter W for the food pathway is based upon X/Q. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Equation [2.3-20] may be expressed for purposes of implementation of 40 CFR 190, discussed in 1/2-ODC-2.04, as follows: Beaver Valley Power Station Procedure Number: ;* .!1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 --- In-Field Reference ODCM: GASEOUS EFFLUENTS Revson: Page Number: 8.3.2.1.2.7 Tritium Dose Equation 3.17E-8(RTTM +RT-v +RTr +R Tr) [0.5(X/Q)pv QTpv +(X/Q) v QT +cv (X/Q)vvQT +(X/Q)tvQT` +(,X/Q)cbQ T + (x/Q) dvQ T + (X/Q) wvQz I cb tv cb dv wv[23-27]wvhere: RT-M = Dose factor for organ "r" for tritium for the milk pathway (mrem!yr per uCi/m 3).RTtv = Dose factor for organ "hi" for tritium for the vegetable pathway (mrem/yr per uCi/m 3).RT uimB = Dose factor for organ." '" for tritium for the beef pathway (mrem/yr per UCi/M 3).p RTTI Dose factor for organ " T" for tritium for the inhalation pathway (mrem/yr per uCi/m 3).Equation [2.3-27] is used to show compliance with 40 CFR 490, as discussed in 1/2-ODC-2.04.The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RT-M is based on [X/Q]: 8.3.2.1.2.8 Tritium Dose Factors For Milk Pathway RTtM ='.KK",FmQFUap(DLFit)a[O ,75(0.5/H)] = mrem/yr per uCi/m 3 [2.3-28]where: K" = A constant of unit conversion (1000 gm/kg).H = Absolute humidity of the atmosphere (8 gm/m 3).0.75 = The fraction of total feed that is water.0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water. Be'aver I Valley Power.Station Procedure Number: Powe Staion1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 65 of 130 and other parameters and values are the same as for RiTM.The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rttv is based on [X/Q]: 8.3.2.1.2.9 Tritium Dose Factors For Vegetation Pathway RTf + ukfg (UL )a [0.75(0.5/H)] V mrem/yr per uCi/m 3 [2.3-291 where all terms have been defined above.The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RTCB is based on [X/JQ]: 8.3.2.1.2.10 Tritium Dose Factors For Beef Pathway RT = K'KfFQUap DFLi)a [0.75(0.5/H)] = mrem/yr per uCi/m 3 [2.3-30]where all terms have been defined above.To show compliance with ODCM CONTROLS 3.11.2.3 and 3.11.2.4, Equation [2.3-211 is evaluated at the controlling pathway location. For Release Modes 1 through 4, the controlling location is a residence 0.89 miles in the NW sector. Inserting appropriate X/Q values from ATTACHMENT F Tables 2.2-4 to 2.2-10 and D/Q values from ATTACHMENT L Tables 2.3-28 to 2.3-34, Equation [2.3-211 becomes: 8.3.2.1.3 Radioiodines and Particulates Dose Determination 3.17E-8 i[[R iG +Ri. ][(0.5)4.22E-10Qi +l.5 6 E-8Qcv +1.56E-8 Gi lv 1 PV Qiv + .55E8Q5E-855E-8Qi +l.56E-8Qi +1.56E-8 VVItv cbdv Qiwv]+Rir [(0.5)7.30E-9Q. +2.O0E-5Qi.v+2.71E-5Qivv I v .pv+ 2.22E -5 Qit + 2.22E-5Q + 2.OOE-5Q 1 +2.00E-5Q. w ltv cb dv W Tle: Beaver Valley Power :Station Procedure Number: U: Beaver~~~ ~ ~ ~ ~ Vale Powe Stto 1YII/2I:ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference Revision:, Page Number: ODCM: GASEOUS EFFLUENTS 2.~2 66 of 1.30 ..< 0.3 mrem (per 31 days), or [2.3-31)< 7.5 mrem (per quarter), or<15.0 mrem (per year),.For tritium, for purposes of implementation of 40 CFR 190, as discussed in 1/2-ODC-2.04, Equation [2.3-28] reduces to: 3.1 7 E-8[RTT + RTX ][(0.5)7.30E-9Qi + 2.00E-5 Qic +2.71E-5Q.w + 2.22E-5Qi. + 2.22E-5 Qicb + 2.00E-5Qidv +2.OOE -5 Q.wv ] [2.3-32]8.3.2. 1.4 Determination of Controlling Location The determination of a controlling locating for implementation of ODCM CONTROLS 3.11.2.3 and 3. 11.2.4 for radioiodines and particulates is a function of:* Radionuclide mix and their isotopic release* Release Mode* Meteorology
- Exposure pathway* Receptor's age The incorporation of these parameters into Equation [2.3-19] results in the respective equations for each Release Mode at the controlling location.In determination of the controlling location for each Release Mode, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of Release Mode and Release Point. For the ground plane exposure pathway, all radionculides (excluding H-3 and C-14) were considered in determination of the controlling location.
For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling location.In determination of the controlling location for each Release Mode, all of the exposure pathways, as presented in ATTACHMENT E Table 2.2-3, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all" vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations. Beaver Valley Power Station ProcedureNu 2 r:DC 2 0 2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 67 of 130 For determination of the controlling location, the highest D/Q and X/Q values for each Release Point and Release Mode for the vegetable garden, cow milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and Release Points of ATTACHMENT D Tables 2.2-2a and 2.2-2b Based upon these calculations, it was determined that the controlling location for Release Modes 1 through 4 is the residence (vegetable garden)/child pathway.For Release Modes 1 through 4,. the controlling Release Point and mix is VV-1 and VV-2.ATTACHMENT J Tables 2.3-2 through 2.3-20 present Ri values for the total body, GI-LLI, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.These values were calculated using the methodology described in NUREG-0133(3'-'3'1) using a grazing period of 6 months.In determination of the controlling location for Release Modes 1-4, ATTACHMENT F Tables 2.2-4 through 2.2-10 are utilized for X/Q's, and ATTACHMENT L Tables 2.3-28 through'2.3-34 are utilized for long term D/Q values. A description of the derivation of the various X/Q and D/Q values is presented in 1/2-ODC-3.0L. Long-term D/Q values for PV-1/2, CV-1, CV-2, VV-1, VV-2, TV-2, CB-2, DV-2 AND WV-2 are provided for the midpoints of the following distances: 0.0-0.5 mi., 0.5-1.0 mi., 1.0-1.5 mi., 1.5-2.0 mi., 2.0-2.5 mi., 2.5-3.0 mi., 3.0-3.5 mi., 3.5-4.0 mi., 4.0-4.5 mi., 4.5-5.0 mi.The values appear in ATTACHMENT K Tables 2.3-21 through 2.3-27. These values may be utilized if an additional special location arises different from those presented in the special locations of ATTACHMENT E Table 2.2-3.The following relationship must hold for BV-I or BV-2 to show compliance with ODCM CONTROL 3.11.2.3.For The Calendar Quarter: D, < 7.5 mrem to any organ [2.3-33]For The Calendar Year: D, < 15 mrem to any organ[2.3-34] Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: .'1 2 68 of1i30 .. where:, D,= The dose to any organ from radioiodines and particulates (mrem).The quarterly limits given above represent one-half the annual design objective of Section II.C of Appendix I of 10 CFR 50. If any of the limits of Equations[2.3-33] and [2.3-34] are exceeded, a Special Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.3.a must be filed with the: NRC at the identified locations. 8.3.2.2 Projection Of Doses (Radioiodines And Particulates) Doses due to gaseous releases from BV-1 or BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit,:when averaged over 31 days, would exceed 0.3 mrem to any organ. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of radioiodines and " particulates will be calculatedfor use ih the 31-day dose projection using Equation[2.3-31]. The 31-day dose projection shall be performed according to the following equations: 8.3.2.2.1 When Includina Pre-Release Data, D 3 1 =[A+B 1 (3 1)+C [2.3-35]8.3.2.2.2 When Not Including Pre-Release Data, D 3 1 =[A] 31i + C [2.3-36]where: D 3t= Projected 31 day dose (mrem).A Cumulative dose for quarter .(mrem).B Projected dose for this release (mrem).T = Current days into quarter.C Value which may be used to anticipate plant trends (mrem). Beaver Valley Power Station ProcedureNumbe ~1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 69 of 130 8.4 Gaseous Radwaste System The gaseous radwaste system has the capability to control, collect, process, store, recycle, and dispose of gaseous radioactive waste generated as a result of plant operations, including anticipated operational occurrences. A simplified flow diagram of the gaseous radwaste system for BV- 1 and BV-2 is provided as ATTACHMENT N Figure 2.4-1. A diagram showing the gaseous effluent Release Points is provided as ATTACHMENT P Figure 2.4-2. Since the concept of a shared gaseous radwaste system is used, then gaseous waste generated can be stored, processed, and discharged from either BV-I or BV-2.8.4.1 BV-1 Gaseous Radwaste System Components 8.4.1.1 BR-1EV-2A/2B: Degasifiers There are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.8.4.1.2 GW-1E-1A/1B: Waste Gas Chillers There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.8.4.1.3. GW-1TK-3A thru 3D: Gaseous Waste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.8.4.1.4 GW-1FL-5A/5B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor -Prefilters. The filters remove carbon solids from the gas stream.8.4.1.5 GW-1C-1A/1B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters. 8.4.1.6 GW-1TK-2: Gaseous Waste Surge Tank) There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually. Beaver Valley Power Station ProcedureNumbe: .....1/2,ODC-2.02 Title: Unit: Level Of Use: 1/2 IIn-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 70 6f 130____2 8.4.1.7 GW-1TK-1A thru 1C: Waste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting-predominant nuclide should be krypton 85.8.4.1.8 RM-1GW-108 And RM-1GW-109: Gaseous Effluent Radiation Monitors There are redundant Radiation Monitors on the combined PV-1/2, Gaseous Waste/Process Vent release path. These Radiation Monitors continuously analyze gaseous waste as it is being discharged. Gaseous Monitor RM-1GW-108B is an off-line gamma scintillator, while RM-1GW-109 Channel 5 is an off-line beta scintillator. The upper activity alarm on the gaseous Channels of these Radiation Monitors have setpoints that would indicate we are approaching the Total Body Dose Rate or Skin Dose Rate limits for radioactive gas leaving the site. If an upper activity alarm on RM-1GW-108B is received, it automatically terminates the discharge by closing an isolation valve downstream of the Decay Tanks.8.4.2 BV-2 Gaseous Radwaste System Components 8.4.2.1 2BRS-EV21A/21B: Degasifiers There are four Degasifiers (two at Unit 1 and two at Unit 2). They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.8.4.2.2 2GWS-E21A/21B: Waste Gas Chillers There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.8.4.2.3 2GWS-TK22A thru 22D: Waste Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit 1 and four at Unit 2). The dry effluent from the Chillers is directed to the.Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.8.4.2.4 2GWS-FLT24A/24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Waste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream. -p Beaver Valley Power Procedure Number:~1/2-ODC-2.02 Title: B e UnitV Level Of Use: 1/[2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 71 of 130 8.4.2.5 2GWS-C21A/21B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through the Prefilters. 8.4.2.6 2GWS-TK21: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.8.4.2.7 2GWS-TK25A thru 25G: Gaseous Waste Storage Tanks There are seven Storage Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Storage Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.8.4.2.8 RM-1GW-108 And RM-1GW-109: Gaseous Effluent Radiation Monitors Previously described in Section 8.4.1.-END - Beaver Valley Power Station I IProduroNumber: Title: Unit: Level Of Use: ,1/2 1 In-Field Reference I_ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 T9) f 1IA T7 ATTACHMENT A Page 1 of 2 GASEOUS SOURCE TERM TABLE 2.1-la BV-I RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr), RX CONTAINMENT/: SLCRS VENT Long Term, And CONTAINMENT BUILDING(" Short Term NUCLIDE(2)Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 2.2E-02 1.5E-01 6.IE+01 5.4E-02 2.4E-01 4.7E-04 7.4E-01 8.9E-01 8.9E+01 4.5E-03 7.0E-0 I 1.0E-03 1.5E-02 2.5E+0 1 AUXILIARY BUILDING VENT AUXILIARY BUILDING VENTILATION Long Term 4.2E-01 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-01 3.6E+0 1 3.2E-0 I 4.5E+00 2.1E-01 1.1 E+00 0.0 GASEOUS WASTE/PROCESS VENT MAIN* CONDENSER/ AIR EJECTOR Long Term 2.7E-01 1.2E+00 1.6E+00:8.2E-01 2.4E+00 7.7E-02 8.OE-02 5.6E-0 1 2.3 E+0 1 2.OE-01 2.8E+00 1.3E-01 6.6E-0 1 0.0 CONTAINMENT GASEOUS VACUUM WASTE PUMPS(3) SYSTEM Long Term Short Term 5.2E-03 0.0 5.5E-02 7.3E-02 L.OE+01 2.3E+02 1.1E-02 0.0 7.OE-02 0.0 4.3E-05 0.0 1.8E-01 1.3E+00 3.1E-01 0.0 2.7E+01 2.3E+01 6.2E-04 0.0 2.7E-01 0.0 8.8E-05 0.0 1.7E-03 0.0 0.0 0.0)(1)(2)(3)Containment can be purged via VV-l (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)Source Term from BVPS-2 UFSAR Table 11.3.1 (3.1.1.2)Original Source Term from Calculation No. UR(B)-262 was adjusted for a factor of 14 increase in pump flowrate due to installation of high capacity pumps during 1 R15. This change in Source Term is documented in Condition Report CR03-04830 and Calculation No. ERS-HHM 014.(3. .1.5) (3.1.1.8) (3.1.3.10) Beaver Valley Power Station Procedure.,,mber: .: 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM:"GASEOUSEFFLUENTS Revision: Page Number:.. ..... 2 73 of 130 ATTACHMENT A Page 2 of 2 GASEOUS SOURCE TERM TABLE 2.1 -lb BV-2 RADIONUCLIDE MIXFOR GASEOUS EFFLUENTS (Ci/yr), SLCRS UNFILTERED PATHWAY Long Term, And CONTAINMENT NUCLIDE(2" BUILDING(') Short Term F I Kr-83m Kr-85m Kr-85 Kr-87 KIr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe- 137 Xe-138 Ar-41 4.OE-05 1.4E-02 6.IE+01 5.3E-06 4.1E-03 0.0 7.2E-0 I 7.6E-0 I 8.4E+0 I 0.0 2.4E-01 0.0 0.0 2.5E+01 SLCRS FILTERED PATHWAY AUXILIARY BUILDING VENTILATION Long Term 4.2E-0 1 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-0I 1.3E-01 8.9E-0 1 3.6E+01 3.2E-01 4.5E+00 2.1E-01 1.1 E+00 0.0 TURBINE BUILDING VENT TURBINE BUILDING VENTILATION Long Term 3.9E-05 1.7E-04 2.3E-04 1.1 E-04 3.5E-04 1.1E-05 1.2E-05 8.1E-05 3.4E-03 2.9E-05 4.2E-04 2. 1E-05 9.7E-05 0.0 MAIN CONDENSER/ AIR EJECTOR Long Term 2.7E-0 I 1.2E+00 1.6E+00 8.2E-0 1 2.4E+00 7.7E-02 8.OE-02 5.6E-01 2.3E+O I 2.OE-0 I 2.8E+00 1.3E-0 I 6.6E-0 I 0.0 CONTAINMENT GASEOUS VACUUM WASTE PUMPS(3) SYSTEM Long Term Short Term 3.7E-04 3.9E-03 7.2E-0 I 7.8E-04 5.OE-03 3.1E-06 1.3E-02 2.2E-02 1.9E-00 4.4E-05 1.9E-02 6.3E-06 1.2E-04 0.0 0.0 1.2E-02 2.3E+02 0.0 0.0 0.0 8.3E-01 0.0 8.2E+00 0.0 0.0 0.0 0.0 0.0 GASEOUS WASTE/PROCESS VENT (' Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)(2) SourceTermn from BVPS-2 UFSAR Table 11.3.2(3.1.2.3) (3) Source Term from Calculation No. UR(B)-262(3. 2 5) B v VProcedure Number: Beaver Valley Power Station , 1/2-0DC-2.02 Title:-Unit: Level Of Use: R r 1/2 In-Field Reference m ODCM: GASEOUS EFFLUENTS Revision: Page Number 2 74 of 130/__wr ATTACHMENT B Page 1 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2a BV-I MONITOR DETECTOR EFFICIENCIES (cpm/uCi/cc) NUCLIDE AUXILIARY BUILDING VENT GASEOUS WASTE/PROCESS VENT Rx CONTAINMENT/ SLCRS VENT Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-13 lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 PRIMARY MONITOR(') RM-VS-101B 9.80 E7 3.88 E5 7.38 E7 1.14 E8 1.39 E8 1.34 E8 2.25 E6 1.26 E7 1.01 E7 7.15 E7 1.12 E8 3.16 E7 i.15 E8 7.17 E7 ALTERNATE MONITOR(2)RM-VS-109 Channel 5 2.39 E7 2.47 E7 2.95 E7 2.11 E7 2.93 E7 3.05 E7 1.56 E7 1.94 E7 1.24 E7 5.70 E6 2.91 E7 2.96 E7 2.66 E7 3.00 E7 PRIMARY MONITOR(') RM-GW- 108B 9.00 E7 3.56 ES 6.78 E7 1.05 ES 1.28 E8 1.23 E8 2.07 E6 1.16 E7 9,24 E6 6.58 E7 1.03 E8 2.91 E7 1.06 E8 6.59 E7 ALTERNATE MONITOR(2)RM-GW- 109 Channel 5 2.43 E7 2.51 E7 3.00 E7 2.14 E7 2.98 E7 3.10 E7 1.59 E7 1.97 E7 1.26 E7 5.80 E6 2.96 E7 3.01 E7 2.70 E7 3.05 E7 PRIMARY MONITOR(') RM-VS- 1 07B 5.16 E7 5.04 E7 9.60 E7 5.16 E7 9.59 E7 9.87 E7 2.94 E7 4.17 E7 2.28 E7 1.51 E7.6.42 E7 1.05 E8 7.35 E7 7.19 E7 ALTERNATE MONITOR(2)RM-VS-I 10 Channel 5 2.57 E7 2.67 E7 3.19 E7 2.28 E7 3.16 E7 3.29 E7 1.68 E7 2.09 E7 1.33 E7 6.15 E6 3.14 E7 3.19 E7 2.87 E7 3.23 E7") The listed detector efficiencies for the respective primary monitors (Victoreen) arecorrected for the reduced pressures observed and documented during operation. (2) The alternate monitors (Eberline SPING Channel 5) efficiencies are corrected for detector unique installation factors. (Pressure corrections are not required for the SPING Monitors.) See Calculation Package ERS-SFL-85-031 for additional information. (3.1 1.4) Procedure Number: Beaver Valley Power:Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: ,. _,. ,.1 2 75 of 130 ATTACHMENT B Page 2 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2b BV-2 MONITOR DETECTOR EFFICIENCIES (cpm/uCi/cc) NUCLIDE()Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe- 133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 SLCRS UNFILTERED PATHWAY 2HVS-RQ101 B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 SLCRS FILTERED PATHWAY 2HVS-RQ109B 5.83E7 7.19E7 8.85E7 6.80E7 8.73E7 8.80E7 4.61 E4 6.06E4 2.94E7 1.55E4 7.48E7 9.07E7 7.74E7 7.90E7 WASTE GAS STORAGE VAULT VENT 2RMQ-RQ303B 3.20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7.DECON BUILDING VENT 2RMQ-RQ30 1 B 3.20E7 3.60E7 3.731E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7 CONDENSATE POLISHING BUILDING VENT 2HVL-RQ1 12B 3,20E7 3.60E7 3.73E7 3.05E7 3.72E7 3.86E7 2.44E7 2.86E7 1.80E7 7.22E6 3.86E7 3.78E7 3.52E7 3.79E7'O)~ Efficiencies from Calculation Package ERS-SFL-86-026.(3' 2.) Beaver Valley Power Station Procedure Number:.:/ : "1/2-ODC-2.02
- I I Title: Unit: Level Of Use: R/2 In-Field Reference ji ODCM: GASEOUS EFFLUENTS Reyision:
Page Number: 2
- 76 of 130 ATTACHMENT C Page 1 of I MODES OF GASEOUS RELEASE Table 2.2-.I 1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IIMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT RP 1; WV-l, Ataxiliary Building Vent(l)RP 2; CV-I, Rx Containment/SLCRS VentM')RP 3; PV-1/2, Gaseous Waste/Process Vent(2)RP 4; VV-2 SLCRS Unfiltered PathwayO )RP 5; CV-2, SLCRS Filtered Pathway Vent(l)RELEASE MODE 1 Aux. Bldg.Ventilation Leakage Collection Exhaust Main Cond. Air Ejector, Waste Gas, Containment Vacuum Contiguous Areas RELEASE MODE 2 Containment Purge(3)Same As Mode 1 Same As Mode 1 Containment Purge (3)Same As Mode I RELEASE MODE 3 Same As Mode I Same As Mode 1 and Containment Purge(3)Same As Mode 1 Same As Mode I Same As Mode I and Containment Purge(3)(4)(4)(4)(4)RELEASE MODE 4 Same As Mode 1 Same As Mode 1 Same As Mode 1 and Containment Purge Same As Mode I Same As Mode I 45?Aux. Bldg.Ventilation RP 6; CB-2, Condensate Polishing Bldg Vento)RP 7; WV-2, Waste Gas Storage Vault Vent(l)RP 8; DV-2, Decontamination Bldg Vent(')RP 9; TV-2, Turbine Bldg VentO 1.(4)(4)(4)(4)(4)(4)(4)(4)(4)(4)(4)(4)NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.( Continuous ground level meteorology is applicable (2) Continuous elevated meteorology is applicable (3) Mode established by purge from one unit, all other release points remain same as Mode 1 (4) Not normally a radioactive release point"-'p, I Der: 1 Title: ODCM: GASEOUS EFFLUENTS ATTACHMENT D Page 1 of 2 RADIONUCLIDE MIX TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)RX CONTAINMENT/
SLCRS VENT AUXILIARY BUILDING VENT GASEOUS WASTE/PROCESS VENT Long Term, And CONTAINMENT BUILDING(') AUXILIARY BUILDING VENTILATION MAIN CONDENSER/ AIR EJECTOR CONTAINMENT VACUUMM PUMPS(,)NUCLIDE(). GASEOUS WASTE SYSTEM Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe 135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 Co-58 C0-60 Mn-54 Fe-59 Sr-89 Sr'90.Cs- 134 Cs-137 C- 14 Ar-41 Short Term 2.2E-02 1.5E-01 6.IE+01 5.4E-02 2.4E-01 4.7E-04 7.4E-0 1 8.9E-01 8.9E+01 4.5E-03 7.OE-0 1 1.0E-03 I1.5E-02 1.2E-03 0.0 2.OE-04 0.0 0.0" 7.5E-04 3.4E-04 2.2E-04 7.5E-05 1.7E-05 3.OE-06 2.2E-04 3.8E-04 1.0E+00 2.5E+0 I Long Term 4.2E-01 1.9E+00 2.5E+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-0 1 3.6E+0 I 3.2E-01 4.5E+00 2.1E-01 1.1 E+00 4.6E-02 0.0 6.7E-02 0.0 0.0 6.OE-02 2.7E-02 1.8E-02 6.OE-03 1.3E-03 2.OE-04 1.8E-02 3.OE-02 0.0 0.0 Long Term 2.7E-01 1.2E+00 1.6E+00 8.2E-0I 2.4E+00 7.7E-02 8.OE-02 5.6E-01 2.3E+01 2.OE-0 I 2.8E+00 1.3E-01 6.6E-0 1 2.1E-02 0.0 3.OE-02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Long Term 5.2E-03 5.5E-02 1.0E+01 1. I E-02 7.OE-02 4.3E-05 1.8E-01 3.1 E-0 I 2.7E+0 I 6.2E-04 2.7E-0 I 8.8E-05 1.7E-03 6.6E-03 3.5E-05 1.2E-03 6.6E-06 2.OE-04 2.2E-04 1.OE-04 6.9E-05 2.2E-05 5.2E-06 9.2E-07 6.9E-05 1.2E-04 0.0 0.0 Short Term 0.0 1.2E-02 2.3E+02 0.0 0.0 0.0 8.3E-01 0.0 8.2E+00 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7.OE+00 0.0 () Containment can be purged via VV-1 (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV- 1/2 (Gaseous Waste/Process Vent)(2) Source Term from BVPS-2UFSAR Table 1 1.3-1(3112) (3) See Note (3) from ATTACHMENT A Table 2.1- Ia (3.1.1.5) (3.1.1.8) (3.1.3.10) Vrocedure Number: Beaver Valley Power Station J r N1u2-ODC-2.02 Title: Unit: Level Of Use: 1/2 _ In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 7&7RAf 1'10 H?'ATTACHMENT D Page 2 of 2 RADIONUCLIDE MIX TABLE 2.2-2b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)NUCLIDE(2) Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 Co-58 Co-60 Mn-54 Fe-59 Sr-89 Sr-90 Cs- 134 Cs-137 C-l1 Ar-41 SLCRS UNFILTERED PATHWAY Loftg Term, And CONTAINMENT BUILDING(1) Short Term 4.0E-05 I.4E-02 6.IE+01 5.3E-06 4.1E-03 0.0 7.2E-0 1 7.6E-0 I 8.4E+0 I 0.0 2.4E-0 I 0.0 0.0 2.7E-05 0.0 2.6E-06 0.0.0.0 7.5E-02 3.4E-02 2.2E-02 7.5E-03 1.7E-03 3.OE-04 2.2E-02 3.8E-02 1.01E+00 2.5E+01 SLCRS FILTERED PATHWAY AUXILIARY BUILDING VENTILATION Long Term 4.2E-01 1.9E+00 2.5E1+00 1.3E+00 3.8E+00 1.2E-01 1.3E-01 8.9E-0 1 3.6E+01 3.2E-01 4.5E+00 2.11E-01 1.1 E+00 4.6E-03 0.0 6.7E-03 0.0 0.0 6.0E-04 2.7E-04 1.8E-04 6.0E-05 1.3E-05 2.OE-06 1.8E-04 3.OE-04 0.0 0.0 TURBINE BUILDING VENT TURBINE BUILDING VENTILATION Long Term 3.9E-05 1.7E-04 2.3E-04 1.1E-04 3.5E-04 1. 1E-05 1.2E-05 8.1E-05 3.4E-03 2.9E-05 4.2E-04 2.1E-05 9.7E-05 6.5E-04 0.0 8.7E-04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MAIN CONDENSER/ AIR EJECTOR Long Term 2.7E-01 1.2E+00 1.6E+00 8.2E-01 2.4E+00 7.7E-02 8.OE-02 5.6E-0 1 2.3E+01 2.OE-0 I 2.8E+00 1.3E-01 6.6E-01 2.1E-02 0.0 3.OE-02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CONTAINMENT VACUUM PUMPS(,)Long Term 3.7E-04.3.9E-03 7.2E-01 7.8E-04 5.OE-03 3. IE-06.1.3E-02 2.2E-02 1.9E-00 4.4E-05 1.9E-02 6.3E-06 1.2E-04 4.7E-04 2.51E-06 8.4E-05 4.7E-07 1.4E-05 1.6E-05 7.4E-06 4.9E-06 1.6E-06 3.7E-07 6.6E-08 4.9E-06 8.4E-06 0.0 0.0 GASEOUS WASTE SYSTEM Short Term 0.0 1.2E-02 2.3E+02 0.0 0.0 0;0 8.3E-011 0.0 8.2E+00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0+.0.0 0.0 0.0 0.0 0.0 7.0E+00 0.0 GASEOUS WASTEIPROCESS VENT Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)(2) Source Term from BVPS-2UFSAR Table I 1.3-2(33" (3) See Section 8.1.1.1 _ _ _ __ _ __ _ __ _ Procedure Number: Beaver Valley Power Station 1r2-ODre2mber Title: Unit: Level Of Use: Title:.1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:__2 79 of 130 0 ATTACHMENT E Pa ge I of I DISTANCES TO RELEASE POINTS> %n OCM 00-C CnO~c 1ý NM V-ý OCý011 N 010 \" Cq C 0C .0 MO 0t CIF -- lýcý cl --0.4)V- r-(N 00 0C0 O-C O V)0~ C14 (71M W (C'4 n C= VI-e M 00 CMC C ) C)' Or--O .V) 0O0r'T -C r 'O :q CM CM CMq -~ Oq clýC) O Ceq O(D 0O 0011 MC) % ON CCt 0t 0ýF-q= T1 CA --00 CM (OOCN Q C) r 'I '* 0W
- C ) (N 00F t-q t-oo ao,r-. W)- 0 D o-%-qý 0' C- f.' ' .4 en .4 I Iý>00 nknC ON00 %0O -7 (D -4)44)g4i 0 1ý 0C C -rr 0 e0 C- 0 `Q WC (- Vo vq C1 0 CO%0C ,O0% CMN r 0\ : C'00 e NN 0% <D 000 V4 qý~~~N ' Rq qT -. -' C C W) ON 00 C1 0nW Mi)(=ý~*0 CM'Cý riCI* > (M 00 ~Cq 0 GM C14~ O (=0OMCMO(=kn QCMC0 %rN-C r-ý0M 0 ON-' 000 eqON o0O14 en-rv 4) CCM.4 en C7 t 0 0 --.0q It 00 t- r- It) 0 (q V) V ) < 0 Sf S) 4-2 '-)' 00)~ r)SfM O 40C) 'IT It (g 0> ~ ~ ~ ~ ~~ ('i> q lýrý41 Cý~~~~ C' z0'0r q -(,r-0 1 Beaver Valley Power Station Procedure Number: 1"i/2-ODC-2.02 Unit: ] Level Of Use: In-Field ReferenceL Title;ODCM: GASEOUS EFFLUENTS Revision: 2 Page.Number:., ATTACHMENT F Page 1 of 7 0-5 MILE DISPERSION PARAMETERS 0 U U V)z 0 U 0 z 0<z 9nC 0 U 0 0 0 U Up z Cn CA oA'C40 0 0 00 %0 r- a, 00 000 0000 C C CD 10 10 00 000001 C0 C) 0CNOC 000 C) ~ 40U 0 0 000 N0 N-00( 00N=N -- , n 10 ý000 CIA-~ 0000 0000 0 0-N0 0000 0 C. t=t0 0 .q -0
- 000 -00 0 k t Z oo tr n C C00 r- It d -e~n w- rci e'j*000C: NO IC! 00 -00 (NON0 00 ItrN 0 00~r r N ---00-o5--o 1-t~- M k 1= .( 0000 C en e enM C 1- ON CY, (00 2 C% t Nen0 0 C 0 00CC 1.0 rýv InNO t 10 ON N C4 C N ~ C0 V CON(00 0 0 e0q( asO'O ON enten %0 eqI )00NO0 0 r4N( ONOO 0000C C 00 In 110 I'D a, -N0.00 -O 0( 0 -00 0000n (NNOONNt ý 0 voenen r-66r- 0ý0C ý n -00 0000C 4 ONONNVzr *.T -4 0 \O 0 0 rnr-C ( 0 n*' 0 (N -)',,I 2 -o (N 0 00 ON , pt.00 , (--.CN ON 0ON r'0 (=>Ný 0ý r M en i 000-NO (N 0~.NO*t~0 00 SIN 0.'~ r'N-~ONNO 1.0 N000 0-0ý(=0-ONNNO r,00 MI 004 M 00 00 I,'t rNN( ( NNO 00 eq0 C/)NC W )V)ý Procedure Number: Beaver Valley Power Station 1/2-ODCo2.02 Title: Unit: Level Of Use: 1/2 IIn-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:...... .2 _81 of 130 ATTACHMENT F Page 2 of 7 0-5 MILE DISPERSION PARAMETERS 000 C 0 r 0 D0 -0 0000DýA o Nr~- e 00 t- 0 n0 0 t-\O C NC, C)00-;4 C --D60 00 O 0e 000 000 o> 0 C4 r~0 MC 0C Z)C 00r -1 0 en eý0r-O 0000' C C en C4i- Ore0 %n 0 n O C4 ~ ~~ ~ ~ --- 4e O 00 7<0 -A (1r 0(11*0 O -C7 00 00C%0Z Mo -ene' en~r ---- q"IT0 en IC0)\z.--k r N~~ci "r~r t0 00 0t C) a C, C W1 CD 0 o en o rr-r eýr 0 .000>06 40ve -t- 0000 C4r kir, or:00 U 0%0 C714n n I 00 000 0000 C A C 0ý 00 0e C4 t- 4~oo or-ren 0 0---C C_ at- 00 r-C>C'J- 0 IO0 I\00~ 00 0 0000M 'T Iq ---ý0ýA a,0 00 00 0-a nr 0 00e 0 0 <9 .~ .D C ......0.' ..C) r- ~ ~ 00 00 eq l C .-- C1 elNOýz ~0 00 t- r- 0 OC14 W1 00 00r Cý o r4 -U0~l ~ ~ l BlS 'Procedure Number: Beaver Valley Power Station I: 1/2-ýODC_2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS.Revis Sion: 1 Page Number:/ATTACHMENT F Page 3 of 7 0-5 MILE DISPERSION PARAMETERS U 0>U0 z U CýU U C6 Z, C N>0 U 0 0 z 0 0 Vl)z'00 -00" C_ --00,00 4 CCN "0 en 0ý en 00 -IT C')ý N NO-000e 0 00 t-en '0 00 en (C'1 -4(1.nNt -;r) 00 NV, N 0 C) C>)N- 00 -:N7'T0C0 C>)00 M 0) '0 Cn 0 ".-1 4n en (ON O 00 ON1 a N'0 C)4 en (ON0 00 N 00 N)'C) ) 000 SON ON 0000 C0 en*eqC' C,1 ciC'NONC0 1 r-0O Nt_ ) %00 N- -'0 Wi i n (ý 1R OONýVI n týr C11-A c W)IU 0-00en00 C'4 ON C-4 "l 0000 r 00 r- 0 M CYN -7 W C 0-00 00 N 0 0 0 N z -000 W) '0 0000 C 0-00r_ 0 00 4NON 0000(-C 00 cl CC- CD rCN 0000 0000 S0 ON ON O000 0000-000 CC '00ý "' 0 141 0%C.4 Mt- '6Ci vi.000 N N N CN UN 00 4/N (I e~N C') ~0 00~*. C~N'0 Cl Cl--I --0 ON cN N0 004/N 0 Wl 0 ri'0 cl 00 NO CD 0t- 0D en 0 ,0 C4 00 0 O00 U NOO C4eW It0 00' M >6 6 r_-0 0 cn0 0 O-\0U 0 C14 C : .n .Ce-It 0 C 0\0 00-Cy*: 6 6 6 C! ! e 000 C)ONCNN>zU 0 000.0 0 ON 000.N 0 01 In N 000q 0 ON 0'0q 05\0- G 0 Ný NO U Z) N'D'p W W ý ýCn W Cn ()):" UW ) o V)V) ) i Beaver Valley Power Station ' Procedure Number: 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 2 83 of 110 ATTACHMENT F Page 4 of 7 0-5 MILE DISPERSION PARAMETERS C-i z 0 0 ZQ[-.,',.z<n <5< U 0 0 z 0 U 0 ,...Z o (/2 (/2 0..In ,AI In0 0 0 0* I 06 0000 C)(> W It 00 r4 00ON1 ) -14nNr N- r 00 N- N -CWN N00Qý : 00 '0 N'sO 0 0 C, (OOn 0'Rt n Z) -C 1, 6 0I Cý 9 0o (D Q 0 wle-Ir14 o c p 0 C000 0000 0p M -N Ci CN r c~09 09 In 0 I O" %' n"R CýO NO -I Nin (=N W1 In W1 0ý 00 V 0nt -InI 0 0 NIz r N II n O NN4 q j N 0 0 C,-tNr In0 O ON r C C 01 4CN .e r C4 =>0 't__ n el; N e-;fl;00k I -00 en N -rn eq M~N 000 C,'IO- 0 -NOMNqýeNi06 ri 0 % CO-4 e 0 .;_N ~ý1- GCqCW1e 'NI" O 0 W1 0I\O NOOO- D 00Ný1ýO0rIr
- % NC'ON eON R000 7ý V 'n n r -7 \oC)'-n r " e- C1 Cý00000:2 NO 00 (0 Cn.4 ID -0 N 0 00 000 In CIA rN 000 N,000 N'- 0 NO,, C! Cl 000 q 00 00--004 Cl 6 Cl.. 0 00 NN 000 000 000 Iln 00 M D00 000C C 0 00 tn 4n NO OA C4 00 ON1 000 C, C 00 O7N 00C C14 C4 C ON W) \0 NO r!Cl0 0 00 04 N -0000 000 4 O 0 C> 0lO 0000 rO-C NOC 0000 0 C0 NO Vý Cl ON 0 'IZ) C) ON)4 l 000 ONnONO0N 0 0 00 00 CD 00 0<In 0 0.* NO ,r 00 NON000 tN -000 N- N -0 0 Ce "cli 0 l 0£a. 1 ,4 vo V, V/
Beaver Valley Power Station J Procedure Number: Title: Unit: Level Of Use: 1/2 In-Field Reference Revision; Page Number: 2 -AR'd f 1-4ODCM: GASEOUS EFFLUENTS--I ATTACHMENT F Page 5 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-8 DV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (1E-7 sec/mr 3)(IDENTIFIED Same as Table 2.2-4'p'p Procedure Number: Beaver Valley Power Station 1/2ed0C-2.02 .. ..1/2-ODC-2.02 Title: Unit: Level Of Use:.1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:.o _. ,: .... .... : 2 25 of 130 ATTACHMENT F Page 6 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-9 WV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q.VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (1E-7 sec/mr 3)Same as Table 2.2-4 Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: LeveI Of Use: T 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _86 2' 130 ATTACHMENT F Page 7 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-10 CB-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS Same as Table 2.2-7 ,?p Beaver Valley. Power Station c1/20DC,2,02 Title: Unit: Level Of Use: S1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2_ 87 of 132 ATTACHMENT G Page 1 of 2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Ki Li Mi Ni TOTAL BODY SKIN DOSE GAMMA AIR BETA AIR DOSE NUCLIDE(') DOSE FACTOR FACTOR DOSE FACTOR FACTOR mrem/yr mrem/yr mrad/yr mrad/yr Per Per Per Per uCi/m 3 uCi/m 3 uCi/m 3 uCi/m 3 Kr-83m 7.56E-02 -- 1.93E+01 Kr-85m 1.17E+03 1.46E+03 1.23E+03 I Kr-85 1.61E+01 1.34E+03 1.72E+01 I Kr-87 5.92E+03 9.73E+03 6.17E+03 I Kr-88 1.47E+04 2.37E+03 1.52E+04 2 Kr-89 1.66E+04 1.01E+04 1.73E+04 I Kr-90 1.56E4-04 7.29E+03 1.63E+04 7 Xe-131m 9.15E+O1 4.76E+02 1.56E+02 I Xe-133m 2.51E+02 9.94E+02 3.27E+02 I Xe-133 2.94E+02 3.06E+02 3.53E+02 I Xe-135m 3.12E+03 7.11E+02 3.36E+03 7 Xe-135 1.81E+03 I1.86E+03 1.92E+03 2 Xe-137 1.42E+03 1.22E+04 1.51E+03 I Xe-138 8.83E+03 4.13E+03 9.21E+03 4 Ar-41 8.84E+03, 2.69E+03 9.30E+03 3 (1) The listed dose factors are for radionuclides that may be detected in gaseous effluents. 2.88E+02.97E+03.95E+03 1.03E+04.93E+03 1.06E+04 7.83E+03.1 IE+03.48E+03.05E+03 7.39E+02.46E+03.27E+04.75E+03.28E+03 A -Procedure Number: Beaver-Valley Power Station ': ioo -o DC-2.. .Title: Uni: 'level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: ,____ __2 _88 of 130_ATTACHMENT G Page 2 of 2 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES (2) .M(3)Vi 1) BiC3 TOTAL BODY GAMMA AIR TOTAL BODY GAMMA AIR NUCLIDE 4-DOSE FACTOR DOSEFACTOR DOSE FACTOR DOSE FACTOR mrem/yr mrad/yr mremlyr mrad/yr Per Per Per. Per uCi/sec uCi/sec uCi/sec uCi/sec Kr-83m 3.19E-10 I 75E-8 4.58E-8 3.96E-5 Kr-85m 7.81E-5 1.16E-4 4.70E-4 7.06E-4 Kr-85 1.55E-6 2.35E-6 5.54E-6 8.40E-6 Kr-87 5.13E-4 7.74E-4 1.45E-3 2.19E-3 Kr-88 1.39E-3 2.09E-3 4.09E-3 6.16E-3 Kr-89 7.99E-4 1.20E-3 1.25E-3 1.88E-3 Xe-131m 1.64E-5 2.47E-5 1.67E-4 3.09E-4 Xe-133m 1.38E-5 2.1 E-5 1.32E-4 2.61E-4 Xe-133 1.05E-5 1.56E-4 1.54E-4 2.76E-4 Xe-135m 2.41E-4 3.66E-4 6.21E-4 9.50E-4 Xe-135 1.41E-4 2.12E-4 6.96E-4 1.05E-3 Xe-137 6.OOE-5 9.05E-5 9.66E-5 1.46E-4 Xe-138 8.11E-4 1.22E-3 2.22E-3 3.34E-3 Ar-41' 1.02E-3 1.53E-3 2.68E-3 4.02E-3 Vi' and Bi values used to implement Modes 1, 2, and 3 of Section 2.2.1 (1OCFR20)(2)Bi values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (1OCFR50)(3) Vi and Bi values to implement Mode 4 of Section 2.2.1 (1OCFR20) and to implement monitor setpoint determinations of Section 2.1.2 and 2.1.4 (4) The listed dose parameters are for radionuclides that may be detected in gaseous effluents. Procedure Number: Beaver Valley Power Station ________Om __e__....__ __ _ _ _ _ __ _ _ _ _ __ _ _ _ _ __ _ _ _ _1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 99 of 130 ATTACHMENT H Page 1 of I ORGAN DOSE PARAMETERS Table 2,2-13 P CILD i TU RBIV1 ALLIT SITI (Wee/yr per uCi/cu later)heclide Bone Liver T. lody Thyroid Kidney Lung G1-LIJ 11-3 0.001+00 1.123,03 1.121+03 1.121+03 1.121+03 1.121+03 1.121+03 2,P-32 2.601+06 1.141+05 9.818+04 0.001+00 0.001+00 0.001+00 4.221+04 3 Cr-51 0.001+00 0.001400 1.541+02 8.551+01 2.431+01 1.701+04 1.081+03 4 In-54 0.001+00 4.291+04 9.511+03 0.001+00 1.001+04 1.581401 2.291+04 5 1c-59 2.071+04 1.671+04 0.001`00 0.001+00 1.271+06 7.071+04 6 Co-57 0.001+00 9.031+02 1.071+03 0.001+00 0.001+00 5.071+05 1.321+04 7 Co-58 0.001+00 1.771103 3.181,03 0.001+00 0.001+00 1.111106 3.441+04 8 Co-60 0.001+00 1.311+04 2.261+04 0.001*00 0.001+00 7.07+06 9.821+04 9 Zh-65 4.251+04 1.131,05 T.031044 0.001+00 7.141+04 9.951+05 1.631+04 10 lb-86 0.001+00 1.981+05 1.141+05 0.001+00 0.001400 0.001+00 7.991+03 I1 Ir-89 5.991+05 0.001400 1.721+04 0.001+00 0.001+00 2.161+06 1.671+05 12 Sr-90 1.011+08 0.001+00 6.441+06 0.001+00 0.001+00 1.481+07 3.431+05 H3 T-91 9.141+05 0.001+00 2.441+04 0.001+00 0.001+00 2.631,06 1.841+05 14 Ir-95 1.901+05 4.181+04 3.701+04 0.001+00 5.961+04 2.231*06 6.111+04 15 Ub-95 2.351+04 9.181+03 6.551+03 0.001+00 8.621+03 6.141405 3.701+04 16 lb-97 4.291-01 7.701-02 3.601-02 0.001900 8.551-02 3.421+03 2.781+04 17 No-99 0.003*00 1.721+02 4.261+01 0.001400 3.921+02 1.351+05 1.211+05 18 Ic-992 1.761-03 3.481-03 6.771-02 0.001+00 5.071-02 9.511+02 4.811+03 19 11-103 2.791+03 0.00100 1.071+03 0.001400 7.031*03 6.621+05 4.481+04 20 lnu-106 1.361+05 0.001100 1.691+04 0.001+00 1.841+05 1.431*07 4.291+05 21 Ag-t110 1.691+04 1.141404 9.144*03 0.001+00 2.121+04 5.488+06 1.001+05 22 W-12N 5.741+04 1.401+02 2.001404 1.261+02 0.001+00 3.241+06 1.641M05 23 $b-125 9.841+04 7.591402 2.071*04 9.101*01 0.001+00 2.321+06 4.031+04 24 7e-127a 2.491*04 8.551*03 3.021*03 6.071*03 6.361+04 1.461+06 1.141+04 25 Ts-129a 1.921+04 6.851+03 3.041*03 6.331+03 5.031+04 1.761+06 1.821+05 26 1-131 4.811+04 4.811+04 2.731+04 1.621+07 7.881+04 0.001+00 2.841+03 27 1-133 1.661+04 2.031+04 7.701+03 3.851+06 3.381+04 0.001+00 5.481+03 28 Ca-134 6.511*05 1.0i1106 2.251,05 0.00o*00 3.301+05 1.211+05 3.851+03 29 Ca-138 0.511+04 1.711+05 1.168105 0.001+00 9.551+04 1.453*04 4.181+03 30 Ca-I31 9.071+05 8.251+05 1.281+05 0.001*00 2.821+06 1.041+05 3.621+03 31 Ba-140 7.401+04 6.481+01 4.331+03 0.001+00 2.111+01 1.741+08 1.021+05 32 Ta-140 6.441+02 2.251+02 7.551+01 0.001400 0.001+00 1.831+05 2.261+05 33 Ce-141 3.921+04 1.951+04 2.901+03 0.001+00 8.551+03 5.441+05 5.661+04 34 Ce-144 6.771+06 2.121+06 3.511+05 0,001+00 1.171+,6 1.201+07 3.891+05 Calculated per ODi equation 2.2-13 Procedure Number: ,,Beaver Valley Power Station ... 1/2.ODC-2.02 Title: Uni t: Level Of Use: 1/2 In-Field Reference m l ODCM: GASEOUS EFFLUENTS Revision: 2 Page Number: QO nf 1M)A ATTACHMENT I Page 1 of 1 MODES OF GASEOUS RELEASE TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT RP 1; VV- 1, Auxiliary Building Vent(I)RP 2; CV-1, Rx Containment/SLCRS Vent(I)RP 3; PV-I/2, Gaseous Waste/Process Vent(2)RP 4; VV-2 SLCRS Unfiltered Pathway(l) RP 5; CV-2, SLCRS Filtered Pathway0') RP 6; CB-2, Condensate Polishing Bldg Vent(l)RP 7; WV-2, Waste Gas Storage Vault Vent(l'RP 8; DV-2, Decontamination Bldg Vent~l!.RP 9; TV-2, Turbine Bldg Vent(')RELEASE MODE 1 Aux. Bldg.Ventilation.RELEASE MODE 2 Containment Purge(3)Leakage Collection Same As Mode 1 Exhaust Main Cond. Air Ejector, Waste Gas, Containment Vacuum, Contiguous Areas Same As Mode 1 Containment Purge(3)Same As Mode 1 RELEASE MODE 3 Same As Mode 1 SameAs Mode 1 and Containment Purge(3)Same As Mode 1 Same As Mode I Same As Mode I and Containment Purge(3)(4)(4)(4)(4)RELEASE MODE 4 Same As Mode I Same As Mode 1 Same As Mode 1 and Containment Purge Same As Mode I Same As Mode 1 Aux. Bldg.Ventilation (4)(4)(4)(4)(4)(4)(4)(4)(4)(4)(4)(4)NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.(1) Continuous ground level meteorology is applicable (2) Continuous elevated meteorology is applicable (3) Mode established by purge from one unit, all other release points remain same as Mode 1 (4) Not normally a radioactive release point Beaver Valley Power Station Procedure Dc2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 2 91 of 130 ATTACHMENT J Page 1 of 19 P&I ORGAN DOSE FACTORS Table 2.3-2 I YALIS 10 FORBUM VAHlIT 5171 (area/yr per uCt/co neter)Pathway Inhalation ige Group zAdult 11clide Bone Liver T. Body Thyroid Kidney Lug G1-LL1 1141 0.001+00 1.261+03 1.261+03 1.261+03 1.261+03 1.281+03 1.281+03 2 1-32 1.321406 7.711+04 5.011+4 0.00+00 0.001+00 0.001+00 8.641+04 3 Cr-51 0.001+00 0.001+00 1.001+02 5.951+01 2.261401, 1.41+04 3.321+03 4 MI-54 M000+00 3.961+04 6.301+03 0.001+00 9.641403 1.401+06 7.741904 5 1e-59 1.181+04 2.781#04 1.061+04 0.001+00 0.001+00 1.021+06 1.881+05 6 Co-5T 0.001+00 6.921#02 9.711+02 0.001+00 0.001+00 3.701+05 3.141+04 7 Co-58 0.001+00 1.581+03 2.071+03_ 0.001+00 0.001+0 9.281+05 1.061+05* Co-60 0.001+00 1.151÷04 1.481+04 0.001+00 0.001+00 5.971+06 2.851+05 9 Zn-65 3.241404 1.031+05 4.661+04 0.001+00 6.901+04 8.641+05 5.34+04 10 lb-8O 0.001+00 1.351+05 5.901+04 0.001+00 0.001400 0.001+00 1.661+04 11 Sr-89 3.041+05 0.001+00 8.721+03 0.001+00 0.001+00 1.401+06 3.501+05 12 Sr-90 9.921+07 0.001+00 6.101+06 0.001+00 0.001*00 9.601+06 7.221405 13 1791 4.621+05 0.001+00 1.241+04 0.001+00 0.001600 1.701+06 3.851+05 14 Zr495. 1.071+05 3.441+04 2.338444 0.001+00 5.421+04 1.771+06 .1.501+05 15 W195 1.411404 7.821603 4.211+03 0.001+00 7.741+03 5.051+05 1.041+05 16 b-97I 2.221-01 5.621-02 2.05142 0.001+00 6.541-02 2.401+03 2.421+02 17 10o79" 0.001+00 1.211+02 2.301+01 0.001+00 2.911+02 9.121+04 2.481+05 18 Tc-992 1.031-03 2.911-03 3.701-02 0.001+00 4.421-02 7.641+02 4.161+03 19 h-103 1.531+03 0.001+00 6.581+02 0.001+00 5.831+03 5.051+05 1.101+05 20 i-lO6 6.911+04 0.001+40 8.721+03 0.001+00 1.341+05 9.361+06 9.121+05 21 Ag-liOn 1.081+04 1.001+04 5.941+03 0.001+00 1.971404 4.831+06 3.021+05 22 Sb-124 3.121+04 5.891,02 1.241+04 7.559+01 0.001+00 2.481+06 4.061+05 23 Sb-125 5.341+04 5.956,02 1.261+04 5.401+01 0.001+00 1.741+06 1.011+05 24 To-127a 1.261+04 5.771+03 1.571+03 3.291+03 4.581+04 9.601+05 1.501+05 25 Te-129m 9.761+03 4.611+03 1.581+03 3.441+03 3.661+04 1.161+06 3:831+05 26 1-131 2.521+04 3.581+04 2.051+04 1.191+07 6.131+04 0.001+00 8.281+03 27 1-133 8.641+03 1.401+04 4.521+03 2.151+06 2.581+04 0.001+00 8.881+03 26 CU134 3.731+05 8.481+05 7.281+05 0.001*00 2.671+05 9361+04 1.041+04 29 CO-135 3.901+04 1.461+05 1.101+05 0.001+00 6.581+04 1.201+04 1.171+04 30 Ca-137 4.781+05 6.211405 4.281+05 0.001+00 2.221+05 7.521+04 8.401+03 31 Ba-i40 3.901+04 4.901+01 2.571+03 0.001+00 1.671+01 1.271+06 2.181+05 32 La-140 3.441+02 1.741+02 4.581+01 0.001+00 0.001+00 1.361+05 4.581+05 33 Ce-141 1.991+04 1.351+04 1.531+03. 0.001+00 6.261+03 3.621+05 1:201+05 34 Ce-144 3.431+06 1.431+06 1.841+05 0.001+00 8.481+05 7.781+06 8.161+05 Calculated per ODai equation 2.3-22 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 92 of i30 ATTACHMENT J Page 2 of 19 P&I ORGAN DOSE FACTORS Table 2.3-3 I VALWIS FOR 8M1 VALIT SIT!(urea/yr per aCI/c aeter)Pathayl Inhalation Age Group -Teen hNlide Bone Liver T. Body Thyroid Kidney Lung 61-ILl 1 1-3 0.001+00 1.271+03 1.271+03 1.271+03 1.271+03 1.271+03 1.271+03 2 P-32 1.691+06 1.101+05 7.161+04 0.001+00 0.001+00 0.001+00' 9.281+04 3 Cr-51 0.001+00 0.001+00 1.351+02 7.501+01 3.071+01 2.101+04 3.001+03 4 #a-54 0.001+00 5.111+04 8.401+03 0.001+00 1.271+04 1.981+06 6.601+04 5 It-59 1.591+04 3.701+04 1.431+04 0.001+00 0.001+00 1.531+06 1.781+05 6 Co-57 0.001+00 9.441+02 k.201+02 0.001+00 0.003+00 5.881+05 3.141+04 7 Co-58 0.001+00 2.071+03 2.781+03 0.001+00 0.001+00 1.341+06 9.521+04 8 Co-60 0.001400 1.511+04 1.981+04 0.001+00 0.001+00 8.721+06 2.591+05 9 Zn-65 3.861+04; 1.341+05 6.241+04 0.001+00 8.641+04 1.241+06 4.661+04 10 Ib-86 0.001+00 1.901+05 6.401+04 0.001400 0.001+00 0.001400 1.771+04 11 Sr-OS 4.341405 0.001+00 1.251+04 0.001+00 0.001+00 2.421+06 3.711+05 12 Sr-90 1.081406 0.001+00 6.681+06 0.001+00 0.001+00 1.651+07 7.651+05 13 Y-91 6.811405 0.001+00 1.771+04 0.001+00 0.001+00 2.9414+0S 4.091+05 14 Zr-95 1.461+05 4.581+04 3.151+04 0.06010 6.741+04 2.691406' 1.491+05 15 1b-95 1. U1+04 .1.031+04 5.661+03 0.001+00 1.001+04 7.51195 9.681+04 1S Ib-97 3.141-01 7.761-02 2.841-02 0.001+00 9.121-02 3.931+03. 2.171+03 17 No-99 0.001+00 1.69602 3.221+01 0.001+00 4.111402 2.691+05 18 Ic-9OS 1.381-03 3.661-03 4.991-02 0.001+00 5.761-02 1.151+0341 6.131+03 19 hu-103 2.103+03 0.001+00 8.961+02 0.001+00 7.431+03 7.831405'. 1.091+05 20 h-lO 9.841+04 0.001+00 1.241+04 0.001+00 1.901+05 1.611+07 9.601+05 21 Ag-IIO. 1.381+04 1.311+04 7.991+03 0.001+00 2.501+04 6.711+06 2.731+05 22 Sb-124 4,301+04 7.941+02 1.681+04 9.761+01 0.001+00 3.346+06z 3.981+05 23 Sb-125 7.381304 8.081+02 1.721+04 7.041+01 0.001+00 2.141+06C 9.921+04 24 Toe-127u 1.801+04 8.1061+03 2.181+03 4.381+03 6.541+04 1.661+06' 1.5911+05 125.Te-129h 1.391+04 6.581+03 2.251+03 4.581+03 6.191+04 1.981+06 4.051+05 26 1-131 3.541+04 4.911+04 2.641+04 1.461+07 8.401+04 0.001+00 6.491+03 27 1-133 1.221+04 2.051+04 6.221+03 2.921+06 3.591+04 0.001+00 1.031+04 28 Co-134 5.021+05 1.131+06 5.491+05 0.001+00 3.7516+05 1.461+05 9.761+03* 29 Co-13i 5.151904 .1.941+05, 1.371+05 0.001+00 1.101+05 1.761+04 1.091+04 30 Ca-137 6.701+05 8.481+05 3.111+05 0.001+00 3.041+05 1.211+05 8.481+03 31 Ba-140 5.471+04 6.701+01 3.521+03 0.001+00 2.281+01 2.031+08 2.291+05 32 La-140 4.790+02 2.361+02 6.261+01 0.001+00 0.001+00 2.141+05 4.871+05 33.Ce-141 2.841+04 1.901+04 2.171+03 0.001+00 8.881+03 6.141+06: 1.261+05 34 Ce-144 4.891+06 2.021+06 2.621+05 0.001+00 1.211+06 1.341+07, 6.641+05 Calculated per 01CK equation 2.3-22 Procedure Number: Beaver Valley Power Station* 1/2-ODC-2.02 Title: Unit: Level Of Use:.!/2 I In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 93 of 130 ATTACHMENT J Page 3 of 19 P&I ORGAN DOSE FACTORS Table 2.3-4 R VAWUIS FOR 51A111 VALLEY SITE lnreu/yr per vCi/cu mater)Pathway Inhalation Ago Group = Child Welide Bone Liver Y. Body Thyroid fidney Lung GI-ILI 1 R-3 0.001+00 1.121+03 1.121+03 1.121+03 1.121+03 1.121+03 1.121+03 2 P-32 2.601+06 1.141+05 9.885+04 0.001+00 0.001#00 0.001+00 4.221+04 3 Cr-51 0.001+00 0.001+00 1.541+02 8.551+01 2.431`01 1.101+04 1.081+03 4 Na-54 0.001+00 4.291+04 9.511+03 0.001+00 1.001.04 1.581+06 2.291+04 5 fe-59 2.071+04 3.341+04 1.871+04 0.001+00 0.001+00 1.271+06 7.071+04 8 Co-57 0.001+00 9.031+02 1.071+03 0.001+00 0.001+00 5.071+05 1.321*04.7 Co-St 0.001+00 1.771+03 3.161+03 0.001+00 0.001+00 1.111+06 3.441+04 8 Co-60 .0.001+00 1.311+04 2.261+04 0.001+00 0.001+00 7.071+06 9.621+04 9 Za-65 4.251904 1.131+05. 7.031+04 0.001+00 7.141+04 9.951+05 1.631#04 10 U7-86 0.001+00 1.981+05 1.141+05 0.001+00 0,001+00 0.001+00 7.991+03 It Sr-f9 5.991405 0.001+00 1.721+04 0.001+00 0.001t00 2.161+06 1.671+05 12 Sr-90 :1.011+08 0.001+00 6.441+06 0.001+00 0.001+00 1.481+07 3.431+05 13 -.91 9,141+05 0.001+00 2.441+04 0.001+00 0.001+00 2.631+06 1.841+05 14 Zr-95. 1.901905 4.181+04 3.701+04 .0.001+00 .5.961<04 2.231+06 6.111+04 15 11-95 2.351t+04 9.181+03 8.551+03 0.001+00 6.621+03 8.141+05 3.701+04 16 Ko-97 4.291-01 7.701-02 3.601-02 0.001+00 8.551-02 3.,421+03 2.761+04 17 1o-99 0.001+00 , 1.721+02 4,261+01 0.001+00 3.921*02 1.351+05 1.271+05 18 Tc-99 .1.781-03 3.481-03 5.771-02 0.001<00 5.071-02 9.511+02 4.811+03 19 hu-103 2.791+03 0.001+0, .1.071+03, 0,008+00 7.031+03 6.21+05 4.481+04 20 ll4B, 1.361+5 0.001t0 1.691+04 0.001+00 1.841+05, 1.431+07 4.291+05 21 Ag-h1O, 1.691604 1.141+04: 9.14.1+03 0.001+00' 2.121404 5.481+06 1,001+05 22 k1-124 5.741<04 7.401+02 2.001+04 1.261+02 0.001+00 3.241<06 1.641+05 23 01-125 9.841+04 7.591+02 2.071+04 9.101+01 0.001+00' 2.321+08 4.031+04 24 Ti-i27% 2.491+04 8.551403 3.021603 8.071+03' 6.381+04 1.481+06 7.141+04 25 Tei-129i 1.321*04 6.811+03 3.041+03 6.331+03: 5,031+04 1.760+06 1.821+05 261-131 4.811+04 4.811+04 2.731+04 1.621+07 7.881+04 0.0010+0 2.841+03 27 1-133 1.681+04 2.031+04 7.709+03 3.851+06 3.381+04 0.001+00 5.481+03 28 Co-134 8.511005-1.011+08 2.251405 0.001+00 3.301+W0 1.211+05 3.851+03 29 C6-136 6 8.511+04 1.711+05 1.161+05 0.001+00 9.551+04 1.451+04 4.181+03 30 Cs-137 9.071+05 8.251+05 1.281+05 0.001+00 -2.821+05 1.041+05 3.6291+03 31 Bh-140 7.401+04 6.481+01 4.331+03 0.001+00 2.111+01 1.741+06 1.021+05 32 La-140 6.441+02 .2.251+02 7.551+01 0.001+00 0.001+00 1.831+05 2.261+05 33 Ce-141 3.921,04 1.951+04 2.901+03 0.001+00 8.551+03 5.441+05 5.661+04 34 Ce.144 6.T77+06 2.121+06 3.611+05 0.001+00 1.171+06 1.201+07 3.891+05 Calculated per ODCH equation 2.3-22 Procedure Number: Beaver Valley Power Station -ro .. m1/2.-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: ,. "__ _ _ _ _ _2 94 of 1 30 ATTACHMENT J Page 4 of 19 P&I ORGAN DOSE FACTORS Table 2.3-5 A VALU FOR BIAVER VALLEY SIT!('re,/y, per uCI/c mleter)Pathay Inhalation Age Group : Infant liodide Bone Liver T. Body Thyroid [idney Luao GI-LLI 10-3 0.001+00 6.471+02 6.471+02 6.471402 6.471402 6.471+02 6.471+02 2 P-32 2.031+06 1.121+05 .1.141+04 0.001+00 0.001+00 0.001+00 1.611+04 3 Cr-51 0.001+00 0.001+00 8.951+01 5.751+01 1.0+01 1.281+04 3.571+02 4 Mn-54 0.001+00 2.531+04 4.981+03 0.001+00 4.981+03 1.001+06 7.061+03 5 Fe-SR 1.361+04 2.351+04 9.481+03 0.001+00 0.001+00 1.011+06 2.481+04 6 co-5t 0.001+00' 6.511+02 6.411*02 0.001+00 0.001+00 3.791+05: 4.861+03 1 Co-58 0.001+00 1.221+03 1.821+03 0.008+00 0.001+00 7.771+05 1.111404 6 Co-60 0.001+00, '8.021+03 1.181+04 0.001+00 0.001+00 4.511406 3.191+04 9Zn-65 1.931+04 6.261+04 3.111+04 0.001+00 3.251+04 5.141+04 10 lb-86 0.001+00 1.901+05 8.821+04 0.001+00 0.001+00 0.001+00 3.041+03 11 S,-89 3.981+05 0.001+00 1.141+04 0.001+00 0.001+00 2.031+06 6.401+04 12 Sr-90 4.091+07' 0.001+00 2.591+06 0.001+00 0.001400 1.121+07 1.311+05 13 T-91 5.881+05 0.001+00 1.571+04 0.001+00 0.001+00 2.451+06. 7.031+04 14 Zr-95 1.151+05 2.791+04 2.031+04 0.001+00 3.111+04 1.751+06 2.171+04 15 Ib-95 1.571+04 6.431+03 3.781+03 0.001+00 4.721+03 4.791+05 1.271+04 1611b-97 3.421-01 7.291-02 2.631402 0.001+00 5.701402 3.321+3 2.691+04 017 0l-99 0.001+00 1.651+02 3.231+01 0.001.00 2.651i02 1.361+05 4.871+04 18 TC 1.401-03. 2.881403 3.721-02' 0.009+00 3.11ý-02 8.111402,. 2.031+03 19 Ru-103 2.021+03 0.001+00 6.791+02 0.001600 4.241403 5.521+05 1.611+04 20 Ru-106 8.681+04 0.001+00 1.091+04 1.071+05 1.161+07 1.61W+05 21 Ag-110a 9.981.+03. 7.221+03 M.03+0 0.001400 1.091+94 3.673+06 3.301+04 22 Sb-124 3.791+04 5.561+02 1.201+04 1.011+02 0.001+00 2.651+08 5.911+04 23 Sb-125 5.171+04 4.771+02 1.091+04 6.231+01 0.001+00 1.641+06 1.471+04 24 Te-127a 1.671+04 6.901+03 2.071+03 4.671+03 3.756404 1.311+06 2.131+04 25 Te-12h 1.411+04 6.091+03 2.231+03 4.211+03 3.161+04 1.681+06 6.901+04 26 1-131 3.791+04 4.441+04 1.961+04 1.481+07 0.001+00 1.083+03 27 1-133 1.321+04. 1.921+04 5.601+03 3.561+06 2.241044 0.001400", 2.161+03 28 Ce-134 3.961+05 7.031+05 1.451+04 0.001+00 1.901+05 7.971+04, 1.331+03 29 Ca-136 4.831+04 1.351+05 5.291+04 0.001+00 5.641+04 1.181+04 1.431+03 30 Ca-137 5.491+05 8.121+05 4.551+04 0.001+00 1.721+05 7.13+04 1.331+03 31 ha-140 5.601+04 5.601+01 2.901+03 0.001400 1.341+01 1.601+06 3.841+04 32 La-140 5.051+02 2.001+02 5.153+01 0.001+00 0.001+00 1.683+05 8.481+04 33 Ce-141 2.771+04 1.671+04 1.991+03 0.001+00 5.259+03 6.171+05 2.161+04 34 Ce-144 3.191+06 1.211+06 1.761+05 0.001+00 5.389+05 9.841+06 1.481+05 Calculated per ODCK equation 2.3-22 .Beaver Valley Power Station .Procedure Number: B r et 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 2 95 of 130 ATTACHMENT J Page 5 of 19 P&I ORGAN DOSE FACTORS Table 2.3-0 i VALIS F01 11Ai01 VALLEY SITU (oq .eter-lres/yr'per mCi/aec)Patbway Ground Iuclide Bone Liver T. Body hyerold Kidney Lung GI-LLI I 9-31 0.001+00 0.00100. 0.001400 0.001*00 0.00100 0.001+00 0.00140 2 P-32 0.001+00 0.001+00 0.00440 0.006*00 0.0014:00 0.001+0 0.o001*00 3 Cr-561 ,.. 4.668306 4.661+06 4.6d1+06 4.661401 4.661*06 4.661+06 4.661*06 4 *Hn-54 1.391*09 1.391*09 1.391+09 1.391+09 1.391*09 1.391+09 1.391*09 5 Fe-59 2.131*08 2.731*08 2.731+08 2.731*08 2.731+08 2.731+08 2.731*08 6 Co-57 0.001*00 0.001+00T00"01+00 0.001400 0.001*00 0.001*00 0.001+00 7 Co-58 3.791*08 3.791+08 3.791*08 3.791*08 3.791+08 3.791+08 3.791*08 6 Co-60
- 2.15110 2.151*10 2.151*10, 2.151+10 2.151+10 2.151*10 2.151*10 9 Zn-65 .7 .471*08 7.471+06 7.471*08 7.471+08 1.471*08 7.471+08 7.471+08 1o Ib-66 8.991+06 6.991*06 6.991*06 8.991*06 8.991*06 6.991*06 8.991+06 It Sr-69 2.161+04 2.161*04 2.161*04 2.161*04 2.161*04 2.161*04 2.161*04-12 Sr+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001*00 0.001*00 13 Y-91 1.071*06 1.071*06 1.071*06 1.071+06 1.071*06 1.071*06 1.071+06 14 Zr-95 2.451*08 2.451*08 2.451*08 2.453*08 2.451*08 2.451*08 2.45106 15 lb-95 1.371*08 1.371+08 1.371*08 1.371*08 1.371+08 1.378*08 1.371+08 16 lib-97 0.001*00 0.001*00 0.001*00 0.001+00 0.001*00 0.001*00 0.001*00 17 No-99 4.001*06 4.001*06 4.001*06 4.001+06 4.001*06 4.001*06 4.00*+06 18 Tc-99 1.841*05 1.841*05 1.041*05 1.841+05 1.843*05 1.841*05 1.841+05 19 bu-103 1.081+08 -1.081+08 1.081*08 1.081*08 1.086100 1.061+08 1.081408 20 11-l06 4.223*08 4,221+08 4.221*08 4.221*08 4.221*08 4.221+06 4.221*08 21 AI-11O. 3.441+09 3.441+09 3.441 109 .3,441*09 3.441+09 3.441*09 3.441+09 22 6b-124 0.001+00 0,001*00 0.001M00 0.001*00 0,001400 0.001*00 0.001*00 23 Sb-25 0.001400 0.001*00 0.00300 0.001*00 0.001+00 0.001*00 0.001+00 24 To-127 A9. 171*04 9.171*04 9.171*04 1 9.011+04 9.171*04 9.171*04 9.171*04 25 Te-129a 1.981÷07 1.981÷07 1.981107 1.981*07 1.981+07 1.981+07 1.981+07 261-131 1.7i1*07 1.72140i 1.72107 1.123*07 1.721+07 1.721407 1.721+07 27 1-133 2.451*06 2.451*06 2.451M06 2.451*06 2.451*06 2.453+06 2.451*06 26 C8-134 6.861+09 6.861,09 6.861*09 6.H61+09 6.686109 6.861+09 6.866109 29 Ca-136 1.511*08 1.511*08 1.511*08 1.513*08 1.511*08 1.511*08 1.511*08 30 Ce-137 1.031*10 1.031*10 1.031*10 1.031*10 1.031410 1.031*10 1.031*10 31 Ba-140 2.051*07 2.051+07 2.051*07 2.051*07 2.051*07 2.051*07 2.051*07 32 La- 1O 1.921*07 1.92147 1.921+07 1.921*07 1.92107 1.921*07 1.921*07 33 Ce-141 1.371*07 1.371*07 1.371*07 1.371*07 1.3V1*07 1.371*07 1.371*07 34 Ce-144 6.961+07 8.961+07 6.96107, 6.961107 6.961+,07 6.961+07 6.961+07 Calculated per ODC0 equation 2.3-23 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number: 2 96_of .130 ATTACHMENT J Page 6 of 19 P&I ORGAN DOSE FACTORS Table 2.3-7 R VIUIS 101 ROIIIJ VAUr SITI (eq meter-mreu/yr per aCi/aec)Patbuy u Vegetation Age Group = Adult Nuclide Bone Liver T. Body Throid Ildey Lung 01-LLI 1 9-3 0.001+00 2.261+03 2.261+03 2.261+03 2.261+03 2.261+03 2.261+03 2 P-32 1.401+09 8 .71+07 5.431+07 0.001+00. 0.001+00 0.001+00' 1.561+08 3 Cr-51 0.001+00 0.001+00 4.641404 2.781+04' 1.021+04 6.161+04 1.171+07 4 1n-54 0.001400 3.131008 5.971+07 0.001+00 9.311+07 0.001+00 9.591405 5 Fe-59 1.261+08 2.961+08 1.141+08 0.001+00 0.001+00 8.281407 9.881+08 6 Co-57 0.001+00 1.171+07 1.951+07 0.001400 0.001+00 0.001+00 2.971+08 7 CO-58 0.001+00 3.071+07 6891+07- 0.001+00 0.001+00 0.001+00 6.231+08 8 CO-60 0.001+00 1.671+08 3.691+06 0.001+00 0.001+00 0.001+00 3.141+09 9 Zn-65 3.171+08 1.011+09 4,561406 0.001+00 6.751+08 0.001+00 6.361+08 10 lb-66 0.001+00 2.191+08 1.021+08 0.001+00 0.001+00' 0.001+00 4.331+07 p 11 Sr-89 9.971+09 0.001+00 2.881+08 0.001+00 0.001+00 0.001+00 1.801+09 12 Sr-O0 8.051+11 0.001+00 1.481+11 0.001+00 0.001+00 0.001+00 13751+10 13 Y-91 5.111+06 0.001+00 1.371+05 0.001+00 0.001+00 0.001+00 2.811+09 14 Zr-95 1.171+06 3.771+05 2.551+05 0.001+00 5.91105 0.001+00, 1;19+09 15 Ib-95 1.421+05 7.921+04 4.281+04 0.001+00 7.03+04 0.001+00 4.811+08 16 lb-97 2.161-0N 5.461-07 1.991-07 0.001+00 6.371-07 0.001+00 2.021-03 17 Io-99 0.001+00 6.151+06 1.171+06 0.001+00 1.391+07 0.001+00 1;431+07 18 Tc-99s 3.101+00 8.7T1+00 1.121+02 0.001+00 1.331+02 4.301+00 <5.191+03 19 h-103 4.771+08 0.001+00 2.061+06 0.001+00 1.821+07 0.001+00 5.571+08 20 hu-108 1.931+08 0.001+00 2.441+07 0.001+00 3.721+08 0.001+00 1.251+10 21 Ag-110i 1.051+07 9.751+08 5.791+08 0.001+00 1.921+07 0.001+00 3.981+09 22 Sb-124 1.041+08 1.961+06 4.111+07 2.511+05 0.001+00 6.071+07 2.941+09 23 Sb-125 1.371+08 1.531.06 3.251+07 1.391+05 0.001+00 1.051+08+. J.501+09 24 Te-127m 3.491+08 1.251+08 4.261+07 8.921+07 1.421+09 0.001400 1.171+09 25 To-129e 2.511+08 9.361+07 3.981+07 8.641+07 1.051+09 0.001+00 1.271+09 26 1-131 8.081+07 1.181+08 6.621+07 3.791+10 1.981+08 0.001+00 3.051+07 27 1-133 2.091+06 3.631+06 1.111+06 5.331+08 8.331+06 0.001+00 3.261+06 28 Ca-134 4.671+09 1.111+10 9L081+09 0.001400 3.591+09. 1.191+09 1.941+08 29 CS-100 4.271+07 1.691+08 1.211+08 0.001+00 9.381+07, 1.291+07 1.911+07 30 Ca-137 8.361+09 8.701+09 5.701+09 0.001+00 2.951+09 9.811+08 1.881+08 31 h-140 1.291+00 1.611+05 8.421+06 0.001+00 5.491+04 9.241+04 2.'651+08 32 La-140 1.981+03 9.971+02 2.831+02 0.001+00 0.001+00 0.001+00 7.321+07 33 Ce-141 1[971+05 1.331+05 1.511+04 0.001+00 8.191+04 0.001400 5.101+08 34 Ce-144 3.291+07 1.381+07 1.771+06 0.001+00 6.161460 0.001+00 1.111+10 All nuclides (except 8-3) calculated per oDCH equation 2.3-28, 1-3 calculated per 03CK equation 2.3-29 9 Beaver Valley Power StationPrcdeNub: Procedure Number: V 1/2.ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 97 of 130 ATTACHMENT J Page 7 of 19 P&I ORGAN DOSE FACTORS Table 2.3-8 11 VLUIS FOR B10M VAULL SiT1 (aq'seter-areu/yr per aCi/sec)Pathway ; Vegetation Age Group z Teen Nuclide Bone Liyer T. Body Thyroid Kidney Lug GI-LLI 18-3 2 7-32 -: 3 CO-5l8:"481n-54 ?5 fe-59, 6 Co*7 B /Co-580 9 ZO-165 10 Rb,86 11 Sr-89 12 Sr490 13 1-91 14 Zr-95 15 WW-95'1 51-97 17 so-99 t8 TC-99n 19 20 lu-100 21 AIg-Orn 22TSb-124 23 24 Te-27rn 25 7e-1294 0.001*00 1.611+00 0.001+60 0,001.00 1.791.08 0.001+00 0.001+00 0.001+00 4.241+06 0.001+00 1.511+10 7.511+11 7.841+06 1.721+06 1.921+05 2.001-06.0.001+00 2.741*00 6.8621+0 2.381+08 1.521+07 1.541+08 2.141+08 5.521+08 3.621+08 2.591+03 2.591603 9.981+07
- 6.241+07 0.001+00 6.171+041+4.541*08 9.011+07 4.191*08 1.621*08 1.791+07 3.008.07 4.361+07 1.001+08 2.491+08 1.4719+09 2.741+08 0.001+00 0.001+00 0.001+00 5.431+05 1.071+05 4.971-07 5.651+05 7.641+00 0.001+00 0.001*00 1.431+07 2.841406 2.341+06 1.961+08 1.341+08 1.081+08 3.291+06 I.mw 1.721+08 1.351+10 1.691+05 8.881+02 1.891605 2.181+07 5.601+08 6.871+08 1.291+08 4.341+08 1.851+11 2.101+05 3.741+05 5.871+04 1.811-07 1.061+06 9.901+01 2.921406 3.901+07 8.721+06 6.021+07 5.011.07 6.561+07, 5.731+07 5.781+07 1.001490 T.751+099 4. 691+09 8.901+06 2.361+02 2.171*04 2.591+03 2.591*03 0.001+00 0.001+00 3.431+04 :1.351+0'4 0.001*00 1.361+08 0.001+00 0.001*00-0.001+0 0.001+00 0.001*00 0.001+00 0.001+00 0.001+00 0.001*00 9.421+08 0.001+00 0.006+00 0.001+00 0.001*00 0.009+00 0.001+00 0.001*00 0.006+00 0.001+00 '7.981+05 0.001+00 1.031+05 0.009+00 5.811-07 0.001+00 1,281+07 0.001+00 1.141+02 0.001+00 2.411+07 0.001+00 5.971408 2.591+03 0.001+00 6.811+04 0.001+00 1.321+08 0. 001+00 0.006+00 0.001+00 0.001+00 0. 001+00 0.001+00 0.006+00 0.001+00 0.001+00 0.006+00 0.001+00 0. 001+00 4.241+00 0.001+00 0.0 0+00 1.351+08 1.6881+08 0.001+00 0.006+00 0.001+00 0.001+00 2.031+09 1. 481+07 1.781+09 1.141+05 0.001+00 0.001+00 0.001+00 2.591+03 1.351808 1.041+07.9.321+08 9.901+08 3.331+08 6.011+08 3.241+09 6.231+08 4.051+07 1.806+09 2.111+10 3.211*09 1.251+09 4.561+08 1.191-02 1.0 11+07 5.021+03 5.701+08 1.481+10 4.031*09 3,111+09 1.871+09 1.371+09 1.361+09 2.131+07 2.4981+06 2.088108 1.391+07 1.921+08*2.131+08 5.101+07 5.411.08 1.331+10 0.001f 00 3.501+05 2.001+05 1.311+06 1.171+06 3.141+10 4.591*08 0. 001*00 0. 001*00 0.001+00 2.741+07 0. 001*00, 0.001o00 2.241+09 1.511.*09 1.851+08 5.77i+66 5.3i+09 9.371+07 4.591+09* 26 1131i. 7.691+07 27 1-.133. 1.94,1+0 26 Ca-134 7.101+09 29 Ca-136 4.381+07 30 CS-137T. 1.011+10 ,.31h -140 1.381+08 32 L67140 1.81n+03 33 Ce-141 2.831#05 34 Ce-144 5.271+07 0.001*00 5.741*04 0.001#+00 0.001+00 0.001+00 8.901+04 0.001+00 1.301+07 All neclidee (except 1-3) calculated per OCKH equation 2.3-26 0-3 calculated per 0DC1 equation 2.3-29 Procedure Number: Beaver Valley Power Station .1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference i ODCM: GASEOUS EFFLUENTS Revision:
.Page Number: 2 .. .98of 130 ;ATTACHMENT J Page'18 of 19 P&I ORGAN DOSE FACTORS Table 2.3-9 I VALOIS FOR B1VI1'VILIAK S911 (sq meter-arel/yr per uCt/see)Patbvay Vegetation Age Group zChild huclide Bone Liver T. Body Thyroid Kidney Lug GI- LI S1-3 0.003+00 4.011+03 4.011+03 4.011+03 4.011#03 4.011+03 4.011+03 2. P-32 3.371+09 .1.581+08 1.301+08.,;0.001+09 0.001+00 0.004+09 9.321+07 3 Cr-51 0.001+00 0.001+00 1.171+05 6.50104t 1.781+04 1.191+05. 6.211+06 4 1n-54 0.001400 6.651+08 1.773+08 0.001+00 1,861+08 0.001+00, 5.581108%5+ fe-59 3.981308 8.431+08 3.201+08 0.001+00 0.001+00 1.871+08 8.701+08 6 Co-57 0.001+00 2.991+07 6..041+07; 0.001+00 0.001t00 0.001+00 2.451+08 7 Co-58 0.001+00 6.441+07 1.971+08 0.001+00 0.001+00 0.001,00 3.761+08 a Co-0 0.001+00 3.761+08 1.121+09 0.001+00 0.001+00 0.001+00 2.101*09 9 Zn-65 8.131+08 2.171+09 1.351+09 0.001+00 1.368+09. 0.001+00 3.801408 10 Rb-86 0.001400 4.521+08 2.761+08 0.001+00 0.001+00 0.001+00 2.911+07 .11 Sr-89 3.601+10 0:001+00 1.031+09 0.00*+00 0,001+00 0.001+00 1.391+09 12 Sr-90 1.241+12 0.001+00 3.151+11 0.001+00 0,001+00 0.001+00, 1.671+10 13 Y-91 1.861+07 0.001+00 4;991+05 0.001+00 0.003+00 0.001+00 2.481+09 14 Zr-95 3.866+06 8.481+05 7.5531+05 0.001+00 1.211306 0.001+00 8.851+08 15 lb-95 4.111+05 1.801+05 +5 0.001+00 1.501+05 0.001+00 2.961+08 16 6b-97 3.651-06 6.591-07 3.081-07 0.001+00 7.311-07 0.001+00 2.031-01 17 No-99 0.001+00 7.711+06 1.911+06 0.001+00 1.651+07 0.001+00 6.381+06 18 Tc-99. 4.711+00 9.241+00 1.531+02 0.001+00 1.341+02 4.691+00, 5.261+03 19 Ru-103 1.531+07 0.001+00 5.901+06 0.001+00 3.861+07 0.001+00 3.971+08 20 h-10 7.451+08 0.001+00 9.301+07 0.00+00 1,011+09 0.1+00. 1.161+10 21 Ag-110r 3.211+07 2.173+07 1.731+07 '0.001+00 4.041+07 0.001+00 2.681+09 22 Sb-124 3.521408 4.5731+06 1.231+08 : 7.771+05 0.001+00 1.951+08 2.201+09 23 Sb-125 4.991+08 3.851+06 1.051408 .4.631+05 0.001+00 2.M81+08 1.191+09 24 Te-127a 1.321+09 3.561+06 1.573+08 3.161+08 3.7711+09 0.001+00 1.071+09 25 Te-129a 8.411+08 2.351+08 1.311+08 2.711+08 2.471+09 0.001+00 261-131 1.431+08 1.443+06 8.171+07 4.781+10 2.361+08 1.281+07 27 1-133 3.531406 4.371.06 1.651*6 8.121+08 7.281+06 0.001400 1.761+06 28 Ce-134 1.601+10 2.6310iO 5.556+09 0.001+00 2.931+09 1'.421+08 29 Cs-136 8.241+07 2.271+08 1.473+08 0.001+00 1,211+08 1.601+07: 7.961+06 30 Co-137 2.391+10 2.291#0 3.381+09 0.001+00 7.461+09 2.681+09 1.431+08 31 Ba-140 2.771608 2.421+07 1.621*07 0.001+00 7.891+04 1.451+05-1.401+08 32 La-140 3.251+03 1.133+03 3.831+02 0.U1+0 0.001+00 .0.001+00 3.161+07 33 Ce-141 6.561+05 3.271+05 4.861+05 0.001+00 1,431+05 0.001+00 4.081+08 34 Ce-144 1.271+08 3.981+07 6.781+06 0.001+00 2.211#07 0.001+00 1.041+10 All nuclides (except 91-3) calculated per equation 2.3-26 H-3 calculated per 001 equation 2.3-29 Procedure Number;Beaver Valley Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: , ___ ___2 99 of 130 ATTACHMENT J Page 9 of 19 P&I ORGAN DOSE FACTORS Table 2.3-10 1 W5 101 R 0 UM VALL Sin (8q meter-area/yr per uCl/eec)Pathway :Heat Age Group Adult luclide Bone 'Liver 7. Body Thyroid Kidney Lung G!-UL!1 9-3 0.001+00 3.251+02 3.251+02 3.251+02 3.251+02 3.251+02 3.251+02 2 P-32 3.951+09 2.461+08 1.531+06 0.001+00 0.001+00 0.001+00 4.441+08 3 Cr4l 0.001+00 0.001+00 5.8611+03 3.501+03 1.291+03 7.781+03 1.471+06 4 bn54 0.001+00 6.491+06 1.241+06 0.001+00 1.931+06 0.001+00 1.991+07 5 2.141+08 5.041+08 1. 1+08 0.001+00 0.001+00 1.411+08 1.681+09 6 Co57` 0.001+00 4.011'06 9.61+66 0.0.01+00 0.001+00 0.001+00 1.021+08 7 Co`07 0.001+00 1.421V07 3.181+07 0.001*00 0.001+00 0.001+00 2.871+08 8 Co-B0 0.0014+0 5.121W07 1.131+08 0.001+00 .. 0.001+00 0.001+00 9.611+08 9 Zn-65 2.541+08 8.091+08 3.861608 0.001 +00 5,411+08 0.001+00 5.101+08 10 Rb-86 0.001+00 4.111+08 1.921+06 0.001+00 0.001+00 0.001+00 8.111+07 11 Sr19 2.411+08 0.001+00 6.921+06 0.001+00 0.001+00 0.001+00 3.871+07 12 Sr-90 8.411+09 0.001+00 2.061+09 0.001+00 0.001+00 0.001+00 2.431+08 U3 T-91 8.941+05 0.001+00 2.391+04 0.001900 0.008+00 0.001+00 4.921+08*14 Zr-9 1.471+08 4.711+05 3.191:05 0.001+00 7.393.+05 0.001400 1.491+09 15 W0295 1,899+06 1.051+.08 5.641+.05 0.O01+i00' 1.049+06 0.001+00 8.371.09 16 Wb-97 0,001#assas amaaauaaaae*a$ 0.001+00 a$sssaaMsas 0.001400 saM$saasaa 17 No-99 .0.001+00 8.511+04 1.621+04 0,001+00 1.931+05 0.001+0 1.971+05 18 Tc.!99n 3.831-21 1.081-20 1.388-19 0.001+00 1.684119 5.301-21 6.401-18 19 h-103 8.571+07 0.001+00 3.691+07 0.001+00, 3.271+08 0.001+00 1.001+10 20 Ru-106 1.971+09 0.00600 2.49108' 0.001+00 3.801+09 0.001+00 1.271+11 2Ag-lb.. 4.771+06 4.411+08 2.621+06 0.001+00, 8.871+08 0.001+0C 1.801+09 22 Sb- ,124 0.00400 0.010oo0 0.010o .+00 0.00600 0.001o00 0.001+0 0.001+00'/-23 sb- 125, 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.009+00 24 Te-127a' 8.381+08 3.001+08 1.021+08 2.141+08 3.401+09 0.001+00 2.811+09 25 Te-129a 9.331+08 3.481+08 1.481+08 3.211+08 3.891+09 0.001+00 4.708+09 26 1-13i 9.131+06 1.311+07 7.481+06 4.281809 2.241+07 0.009+00 3.451+06.27 1-133 3.121-01 5.42,:01 1.651-01 7.96+01 4 9.461-01 .0.001+00 .4.871-01 28 Ca-,134, 4.531+08 1.081+09 8.811+08 0.001+00 3.491+08 1.161+08 1.891+07 29 CS-136 1.021+O 4.041*07 2.911+07 0.001.00 2.251*01 3.08*06 4M.591+06 30 Ca-137 5.901408 8.061+08 5.281408 0.00i+00 2.741+08 9.101+07 1.561+07 31 Ba140 2.441+07 3.061404 1.601+06 0.001+00 1.041+04 1.751+04 5.021+07 32 La&140 .3.161-02 1.591-02 4,211-03 0.001+00 0.001+00 0.001+00 .1.171+03 33 Ce-141. 1.161+04 7.831+03 8.881+02 0.001+00 3.641+03 0.009+00 2.991+07 34 Ce-144 1.031+06 4.321+05 5.551+04 0.001+00 2.56 +05 0.001+00 3.501+08 All nuclides (except 1-3) calculated per 01DC equation 2.3-25 8-3 calculated per OWNII equation 2.3-30
Number:. -Beaver Valley Power Station ,ir:c 1/ 6 -oC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference _ODCM: GASEOUS EFFLUENTS Revision: Page Number: S2 " 100 of1130 0 ATTACHMENT J Page 10 of 19 P&I ORGAN DOSE FACTORS Table 2.3-11 R VAIMS 703 MM*11! VALLIY SITE (eq aeter7meu/yr per uCi/aec)Pathway Heat Age Group : Teen hclide Bone Liver T. Body Thyroid Kidney Long GI-LI 1 H-3 0.001+00 1.94S*02 1.941+02 1.941+02 1.941+02 1.941#02 1.941+02 2 P-32 3.341+09 2.071+08 1.293+08 0.001+00 0.00100 O0.001*+00 2.801*08 3 Cr-41 0.001+00 0.001+00 4.689103 2.601+03 1.039+03 8.691+03 7.881905 4 N-54 0.001+00 4.951+06 9.81A 05 0.001+00 1.481+06 0.001+0 1.011+07 5 7e-59 1.711+08 4.001408 1.541+08 0.001400 0.009+00 1.2614086 9.451+08 6 Co-57 0.001*00 3.221306 5.401*06 0.001+00 0.001+00 0.001*00 6.011+07 7 Co-58 0.001+00 1.091+07 2.521+07 0.001*00 0.001*00 0.001400 1.511*08 8 Co-60 0.001*00 3.971*07 8.951*07 0.001+00 0.001*00 0.001*00 5.171+08 9 Ea-65 1.791608 6.211+08 2.901+08 0.001+00 3.971+08 0.001*00 2.631+00 p 10 Ib-86 0.001*00 3.431+08 1.611*08 0.001+00 0.001+00 0.001400 5.081407 II Sr-89 2.031*08 0.001+00 5.831*06 0.001+00 0.001*00 0.001+00 2.421+07 12 Sr-90 5.443+09. 0.001+00 1.341*09 0.001+00 0.003*00 0.001+00 1. 531f08 13 Y-91 7.531+05 0.001#06 2.021*04 0.001300 0.001+00 0.001400 3.091+08 14 Zr-5 1.131i+00 3.711+05 2.551,05 0.003600 5.451+05 0.00100 8.581+08 15 Ib-95' 1.471W06 8.171*05 4.501+05 0.001*00 7.921*05 0.001400 3.491+09 16 gb-97,. sesassa esenszae sse** 0.001+00 a**artsne 0.001*00 *eeasstste, 17 Ho-9S 0.001+00 7.031+04 1.341904 0.001+00 1.611+05 0.001900 1.261+05 18 To-99S 3.04M-2i 8.481-21 1.101-19 0.001+00 1.281-19 4.711-21 5.571-18 19 h-103 6.981407 0.001+00 2.881f+07 0.001+00 2.461+08 0.001200 5.831+09 20 Ru-106 1.281*09 0.001+00 2.091*08 0.001;00 3.191+09 0.001+00' 7.941+10..21 Ag-l1Oa 3.611+06 3.421+06. 2.081+06 0.001+00 6.521+0. 0.001+00 9.801*08 22 Sb-124 , 0.001+00 0.001400 0.001*00 0.001+00 0.00MW00 0.001+00. .0.001*00 23Sb-0125 0.001400 0.001*00 .0.001.00 0.0016+000.001+006 0.001600', 0.001+00 24 Te-127n 7.071+08 2.511+08 8.411+07 1.681830 0.001400V 1.7817+09 25 Te-129a 7.821*08 2.901+08 1.2414608 2.521308 3.271409 0.001+00 '2.931*09 26 1-131 7.591+06 1.061+07 5.711M08 3.101*09 1.831+07 0.001*00 2.101+06 27 1-133 2.611-01 4.421-01 1.351-01 6.171+01 7.751-01 0.001+00 3.341-01 28 Co-134 3.609+08' 8.483+08 3.931*÷08 0.001+00 2.691+06 1.031608 1.051907 29 Ce-138 7.981+06 3.141+07. 2.111*07 0.001*06 1.711+07 2.691+06 2.531+06 30 Ca-137 4.901+08 4.511408 2.271+08 0.001300 2.221808 8.611+07 9.271906 31 Ba-I10 2.021*07 2.471*04 1.301+08 0.001+00 8.381303 1.661*04 3.113407 32 La-140 2.601402 1.281-02 3.401-03 0.009+00 0.001*00 0.001400 7.331*02 33 Ce-141 9.721H03 6.491+03 7.461+02 0.001+00 3.061+03 0.001*00' 1.861+07 34 Ce-144 8.721905 3.611*05 4.681904 0.009+00 2.151+05 0.001*00 2.191+08 AIl nuclides (except 8-31 calculated per OCH equation 2.3-25 H-3 calculated per ODCH eution 2.3-30 Procedure Number: Beaver Valley Power Station .1/2-ODC-2.02 Title: Unit: Level Of Use:..1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 101 of 130 ATTACHMENT J Page 11 of 19 P&I ORGAN DOSE FACTORS Table 2.3-12 I VHLIS FOR BIUA VDALT SIT!(#q seter-ures/yr per uCI/aec)Patbhay Heat Age Group : Child Nuclide Bone Liver T. Body nTyroid Kidney Long GI-LI 1 1-3 0.001100 2.341*02 2.341*02 2.341902 2.34102 2.341+02 2.341+02 2 P-32 6.291109 2.941+08 2.431+08 0.001+00 0.001+00 0.001*00 1.741+08 3 Cr-51 0.001+00 0.001*00 7.311103 4.06113 1.111+03 7.411*03 3.881+05 4 Hn-54 0.001+00 5.681M06 1.511*06 0.001*00 1.591+06 0.001*00 4.751+06 5 Fe-59 3.041*00 4.911*08 2.451908 0.001+00 0.001400 1.42608 5.121+08 6 Co-57 0.001400 4.211+06 9.521+06 0.001*00 0.001.00 0.00140 3.451+07 7 Co-58 0.001*00 1.281+07 3.911*07 0.001i00 0.001+00 0.001+00 7.451*07 8 CO-60 0,001400 4.7212J67 1.391*08 0.001+00 0.001+00 2.611÷08 9 ZnI65 2.68M*08 7.151608 4.441*08 0.001*00 4.501*0 0.001*00 1.251*08 10 ib-86 0.001+00 4.871+08 2.991*08 0.001*00 0.001+00 0.001+00 3.131+07 11 Sr-89 3.851+08 0.00100 1.101*07 0.001*00 0.001+00 0.001-00 1.491*07 12 Sr-90 7.031409 0.001*00 1.781+09 0.001+00 0.001*00 0.001*00 9.4+17 13 T-91 1.421+06 0.001+00 3.611+04 0.001+00 0.001+00 0.001300 1.901*08 14 Zr-95 2.091+06 4.591*05 4.091*05 0.001+00 6.571*05 0.001400 4.791*08 15Ob-95 2.541*06 9.901*05 7.071*05 0.001*00 9.301*05 0.001*00 1.831+09 1i6 lIb97 stleaan lls+$lSlll3lln 0.001400 tlllessllll 0.001+00 slststSeSl 10 o-.99 0.001*00 9.791*04 2.421404 0.001+00 2.091+05 0.001+00 8.091*04 18Tc-999 5,331-21 1.051-20 1.731-19 0.001*00 1.523-19 5.311- 21 5.951-18 19 1.281+08 0.00100 4.851+07 0.001400 3.J'81+08 0.O0v01+0 3.20419 20 u10ý46 3A121+09 0.001400 3.891*06 0.001400 4.211+09 0.001*0 4.051*10 21 ag'-IlOa 5.991+06 4.04146 3.231*08 0.001300 7.531*06 0.001*00 4.811*06 22 Sb1i24 0.001300 4 .001*00 0.001400 0.001+00 0.00140 0.001400 0.001*00 23 S6 25' 0.00660 0.001*00 0.. 0.00140 0.0013+0 0.001+00 0.001*00..24 .e127 1:331309 3.591*08 1.581081 3.193*09 3.801309 0.001+00 1.081+09 25 Te-129a 1.471+09 4.111*08 2.291*08 4.751*08 4.331+09 0.001*00 1.801+09 28 1131 1.411+07 1.421*07 8,04146 4.681+09 2.321*07 0.001+00. 1.261*06 1 27 1-133 4.841-01 5.99141 2.27141 1.111402 9,981-01 0.001*00 2.411-01 28 Ca134 8.351*08 1.041*09 2.201*18 0.001*00 3.231*08' 1.161+08 5.621*29 Cal136 1.381+07 3.781*07 2.451007 0.001*00 2.011*07 3.001*0 1.331*6 30 Ce-137 9.021+08 1.27TS08 0.00i+00 2.813*08 1.013*06 5.401*06 31 Ba-140 3.721*07 3.281+06 2.171*6 0.001*00 1.061+04 1.941*04 1.693*07 32 La-140 4.761-02 1.661402 5.11143 0.001*00 0.001*00 0.001*00 4.631*02 33 Ce-141 1.631*04 9.131*03 1.38*04 0'061*00 4.001*03 0.001600 1.141*07 34 Ce444 1.641*08 5.1515 8.77144 0.001+00 2.851+05 0.001*0 i+.349+08 All nuclides (except M-3) calculated~per 0DC equation 2.3-25 9-3 calculated per OICH equation 2.3-30 Procedure Number: Beaver Valley Power Station r .ou/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 102 of 130 ATTACHMENT J Page 12 of 19 P&I ORGAN DOSE FACTORS Table 2.3-13 R VYAWS FOR 3V1IK IALLIT SITE (aq aeter-area/yr per uC/leec)Pathway Cov Milk Age Group Adult NWcide Bone Liver 7. Body Thyroid Kidney Lung GI-LLI I 0-3 0.001+00 7.631+02 7.311+02 7.631+02 7.631+02 7.631+02 7.631+02 2 P-32 1.451+10 9.011+06 5.601+08 0.001400 0.001+00 0.001+00 1.631+09 3 Cr-51 0.001+60 0.001+00 2.381+04 1.421+04 5.241+03 3.151404 5.981+06 4 Ma-54 0.001+00 5.951+06 1.131+06 0.001100 1.771+06 0.001+00 1.821+07 5 le-59 2.406.07 5.631+07 2.161+07 0.006+00 0.001+00 1.571+07 1.881+08 6 Co-57 0.001+00 .9.101+05 l511+06 0.001+00 0.001+00 0.001+00 2.311+07 7 Co-58 0.001+00 3.671406 8.221+206 0.001+00 0.400100 0.001400 7.431+07 , 8Co-60
- 1. 1294T0 2.461i07 O.001+000 0.001+00 O.001+00 2.101.08 9 ZA-65 9.801+08 3.121+09 1.411+09 0.001+00 2.091+09 0.001400 1.961+09 10 lb-86 0.001400 2.191+09 1.021+09 0.001+00 0.001+600 0.001+00 4.321+08 )11 Sr-89 1.161+09 0.001+00 3.331+07 0.001+00 0.001+00 0.001+00 1.661+08 12 Sr-90 3.161410 0.001400 7.761+09 0.0014+0 0.001+00 0.001+00 9.141+08 13 Y-91 6.781+03 0.001+00 1.811+02 0.001+00 0.001+00 0.001+00 3.731406 14 Zr-95 7.401+02 2.371+02 1.611+02 0.001+00 3.721+02 0.001+00 7.521+05 15 Nb-95 6.771+04 3.771+04 2.031+04 0.001+00 3.721+04 0.001+00..
2.291408 16 Nb-97 2.811-12 7.111-13 2.601-13 0.001+00 8.301-13 0.00100 2.621-09 17 No-99 0.001+00 2.111+07 4.011+06 0.001+00 4.771+07 0.001,00 4.881+07 18 fn-99i 2.831+00 7.991+00 1.O10102 0.001+00 1.211+02 3.911400. 4.731+03 19 h7103 8.291+02 0.001+00 3.571602 0.001+00 3.161+031 0.00100 9.681+04 20 b-106 1.431+04 0.001600 1.811*03 0.001+00 2.771+04 0.006400 9.271405 21 Ag-lOa 4.161+01 3.841+07 2.289+07 0.001+00 7.569+07,. 0.001+00 1.571+10 22 Sb-124. 0.001+00 0.001+00 0.001+00 0.061+00 0.001+00 0.001+00 0.001+00 23 Sb-125, .0.001+00. 0.001+00 0.001+00. 0.009+00 0.001+00.. 0.001+00 0.001+00 24 Te-127, 3.441+07 1.231+07 4.191.06 8.191+06 1.401+08; 0.001400 1.151+08 25 Te-129i 4.951+07 1.851+07 7.841+06 1.701+07 2.071+08 0.001+00 .2.491+08 26 1-131 l. 2.521+08 3.601+08 2.061+08 1.181+11 6.171+08 0.001+00 9.501+07 27 1-133 3.291+06 5.721+06 1.751+06 8.411+08 9.991+06 0.001400 5.141+06 28 Co-134 3.891+09 9.271+09 7.561+09 0.001+00 3.001+09 9.961+08 1.821+08 29 Ca-136 2.231+08 8.821+08 6.3515+08 0.001+00 4.911+08 6.731607 1.001+08 30 Ce-137 6.821+09 4.471+09 0.001+00 2.321+09 7.701+08 1.321+08 31 Ba-140 2.281+07 2.871+04 1.491+6 0.001+00 9.741+03 1.641+04 4.701+07 32 La,140 3.841+00 L931+00 5AI-OI 0.001+00 0.001+00 0.001+00 1.421+05 33 Ce-141 3.991+03 2.701+03 3.066;02 0.001+00 1.251+03 0.001+00 1.031+07 34 Ce-144 2.541+05 1.066+05 1.36O4WN 0.001+00 6.291+04 0.01+00 8.581+07 All nuclides (except 9-3)Lcalculated per ODL)( equation 2.3-24 R-3 calculated per ODCH equation 2.3-28 ,j Beaver Valley Power Station Pro/cdueNul2iODC_ 2.0 2 Title: Unit: Level Of Use:*1/ In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:_ _______2 103 of 130 ATTACHMENT J Page 13 of 19 P&I ORGAN DOSE FACTORS Table 2.3-14 I VAWIS FORl9IBM VOILILY (eq mter-isa/yr per uCi/sec)PatbWay Co, Milk Ige Group : Teen Nuclide Bone Liver 1. Iody Thyroid lidney Lu" GI-LLI 11t-3 0.001+00 9.941+02 9.941+02 9.941+02 9.941+02 9.941+02 9.941+02 2 P-32 2.971+10 1. 11+09 1.041+09 0.001+00 0.001+00 0.001+00 2.251*09 3 Cr-51; 0.00100 0.001+00 4.151*04 2.311+04 9.101+03 5.931+04 6. 97106 4 1n154 0.001,00 9.911+06 1.961+06 0.001+00 2.951+06 0.001+00 2.031+07 5 1e0S9 4.181+07 9.761+07 3.771i07 0.001+00 0.001+00 3.081+07 2.311+08 6 Co-57 0.001+00 1.601+06 g.681+06 0.001+00 0.001+00 0.001+00 2.981b07 SCo-58 0.001+00 6.171506 1.421+07 0.001+00 0.001+00 0.001+00 8.511+07 8 Co-60 0.001+00 1.891+07 4.261+07 0.001+00 0.001+00 0.001+00 2.461+08 9 Zn-65 1.511+09 5.231+09 2.441+09 0.001+00 3.341+09 0.005+00 2.211+09 10 lb-86 0.001+00 3.991+09 1.871+09 0.001+00 0.001+00 0.001+00 5.911+08 11 Sr-89 2.141+09 0.001+00 6.121+07 0.001+00 0.001+00 0.001+00 2.551+08 12 Sr-90 4.471+10 0.001+00 1.101+10 0.001+00 0.001+00 0.001+00 1.251*09.13 1-91 1.251+04 0.001*00 3.351+02 0. 00100 0.001+00 0.001+00 5.111*08 14 Zr-95 1.291+03 4.081+02 2.811+02 0.001+00 6.001*02 0.001+00 9.421+05 15 lb-95. 1.161+05 6.411,04 3.531+04 0.001+00 6.211+04 0.001+00 2.741+08 16 Wo-94 5.131-12 1.271-12 4.651-13 0.001+00 1.491-12 0.001+00 3.041-08 17 go-99 0.001+00 3.801,07 7.251+08 0.001+00 8.701+07 0.001+00 6.811*07 18 Tc-99S 4.901+00 1.371+01 1.771+02 0.001+00 2.041+0? 7.591+00 8.961+03 19 lu-103 1.471+03 0.001+00 6.301+02 0.001+00 5.201+03 0.001+00 1.231+05 20 h-106 2.031+04 0.001400 3.321+03 0.001+00 5.061+04 0.001*00 1.261*06 21 Ag-liOa 6.871+07 6.501+07 3.951+07 0.001+00 1.241+08 0.001+00 1.831+10 22 Sb.124" 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 23 Sb:125: 0.001+00 0.001+00 0.001+00 0.005+00 0.001+00 0.001+00 0.001+00 24 Te-127v 6.341+07 2.251*07 7.541+06 1.511+07 2.571+08 0.001+00 1.581+08'25 Te-129i 9.061+07 3,361+07 1.431+07 2.921+07 3.791+08 0.001+00 3.401+08 26 1-131 4.571+08 6.391+08 3.431+08. 1.871+11 1.101+09 0.001+00 1.261+08 271-133 6.011+06 1.025+07 3.111+0 1.421+09 1.791+07 0.001+00 7.711+06 28 Ca-134C 6.761+09 1.591+10 7.381+09 0.001+00 5,061+09 1.931+09 1.981*08 29 Cr.136;: 3.801+08 1.501+09 1.011+09 0,001+00 8.151+08 1.281+08 .1.201+08 30 Ce-1371 9.051+09 1.201+10 4.191+09 0.001+00 4.101*09 1.591+09 1.711+08 31 ka-140 4.121+07 5.051*04 2.651+06 0.001+00 1.711+04 3.391+04 6.351*07 32 La-140' 6.891+00 3.391+00 9.011;01 0.001+00 0.001+00 0.001+00 1.941*05 33 Ce-141 7.321+03 4.891+03 5.621+02 0.001+00 2.301+03 0.001*00 1.401+07 34 Ce-144 4.671+05 1.935*05 2.511+04 0.001*00 1.151+05 0.001+00 1.171+08 1l nuclldee (except 9-3) calchlatedper ODCd equation 2.3-24 8-3 calculated per OWNC equation 2.3-28 Beaver Valley Power Station /2-ODC-2.02rcedue Title: Unit:Level Of Use:____ In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: .Page.Number: 2164 of '130Q.ATTACHMENT J Page 14 of 19 P&I ORGAN DOSE FACTORS Table 2.3-:15 a VALS 1013SIM VILLIT 'SITI (sq aeter-ara/r per uCi/aee)Pathway Cow milk Age Group Child Nuclide Bone Liver T. Body Thyroid Kidney Luog I-LLI 1 1-3 0.001060 1.571+03 1.513+03 1.571#03 1.576*03 1.571+03, 1.571+03 2 1-32 6.59V+10 3.091+09 2.541.09 0.001+00 0.001+00 0.001+00 1.321+09 3 Cr-51 0.001+00 0.001+00 8.461+04 4.701+04 1.281+04 8.581404 4.491+06 4 8n-54 0.001+00 1.481+07 3.951+06 0.001+00 4.181+06 0.001+00 1.241+07 5 Ie-59 9.701+07 1.571+08 7.821+07 0.001+00 4.551+07' 1.631+08 6 Co-57 0.001+00 2.731+06 5.521+06 0.001400 0.001+00 0.001+00 2.241+07 I Co-s5 0.001+00 9.431+06 1.891.07 0.001400 0.001+00 0.001+00 , 5.501+07 8 Co-60 0.001+00 2.941+07 8.671+07 0.001+00 0.001+00 0.001400 1.631+08 9 Zn165 2.951+09 7.871+09 4.891+09 0.001*00 4.961+09 0.001400;: 1.381+09 10 b-86 0.001+00 7.401+09 4.551+09 0.001+00 0.001+00 0.001+00' 4.761+08 11 Sr-89 5.291+09 0.001+00 1.511+08 0.001+00 0.001+00 0.001+00 2.051+08 12 Sr-90 7.551+10 0.001+00 1.911+10 0.001+00 0.003+00 0.001+00 1 4021+09 13 T-91 3.081+04 0.001+00 8.241+02 0.001+00 0.001+00 0.001+00 4.111+06 14 Ur-95! 3.001+03 6.801+02 5.881+02 0.001+00 9.451+02 0.003+00 6.891+05 15 Ob-95 2.611+05 1.021+05 7.261404 0.001+00 9.541+04 0.001400 1.861+08 16 lb-97 1.251-11 2.251-12 1.051-12 0.001400 2.50112 0.001+00 0.941-07 17 Ko-99 0.001+00 6.921+07 1.711+07 0.001+00 1.481+08 0.001+00 5.721+07 18 Tc-991 1.121+01 2.20M+01 3.851#02 0.001+00 3.201+02 1.121+01 1.251+04 19 h2-103 3.491+03 0.001+00 1.341+03 0.001+00 6.781+03 0.001+00. 9.011+04 20 h-lO 6.491+04 0.003+00 8.103+03 0.001+00 8.761+04 0.001+00 1.011+06 21 Ag-l10a 1.491+08 1.011+08 8.051+07 0.001+00 1.871+08 0.001+00:. 1.201+10 22 Sb-124 0.001+00 0.001+00 0.001+00 0.001+00 0.001400 0.001+00 0.001+00 23 Sb-125 0.001+00 0.001+00 0.001+00 0.001+00 0.001400 0.001+00..ý 0.001+00 24 Te-127a 1.561+08 4.211+07 1.861+07 3.741U07 4.481+08 0.001+00, 1.271+08 25 Te-129 2.231+08 6.241+07 3.471+07 7.201407 6.561+08 0.001+00 2.721+08 26 1-131 1.111+09 1.111+09 6.331+05 3.681411 1.831+09 0.001+00 9.921+07 27 1-133 1.461+07 1.811307 6.831+06 3.361409 3.011+07 0.001+00 7.281+06 28 Ce-134 1.561+0 2.561+10 5.401+09 0.001+00 7.931+09 .2.851+09 1, *.381+08 29 C91-36 8.581+0U 2.383+09 1.531+09 0.001+00 1.261+09 1.871+06 8.291+07 30 Ce-137 2.181+10 2.091410 3.081+09 0.001+00 6.801409 2.451+09 1.311*08 31 8a-140 9.941+07 8.713+06 5.801+06 0.001+00 2.841+04 5.191+04 .5.041+07 32 La-140 1.651+01 5.771+00 1.941+00 0.001+00 0.001+00 0.001+00, 1.611+05.33 Ce-141 1.801+04 8:991+03 1.341+04 0.001+00 3.941+03 0.001+00 1.12R+07 34 Ce-144 1.151+06 3.611+05 6.151+04 0.001+00 2.001+05 0.001+00 9.411+07 All nuclides (except 8-3) calculated per OCH equation 2.3-24'9-3 calculated per 01CH equation 2.3-28 Procedure Number: Beaver Valley PowerStation 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 105 of 130 ATTACHMENT J Page 15 of 19 P&I ORGAN DOSE FACTORS Table 2.3-16 I VALOIS FOR HAVl VILLY7 SITU (sq eter-uremulr per Pathgay Coc Hilk Age Group : Infant Wiuclde Bone Liver T. Body Thyroid lidoey Loung GI-ALI t H-3 0.001+00 2.381+03 2.381+03 2.381+03 2.381+03 2.381+03 2.381+03 2 P-32 1.381+11 7.991+09 5.273+09 0.001+00 0.60040 0.001+00 1.841+09 3 Cr-1 0.001+00 0.001+00 1.341+05 8.751+04 1.911404 1.701+05 3.911+06 4 Mn-54 0.001+00 2.761+07 6,251406 0.601400 8.111+06 0.001+00 1.011+07 5 FG-59 1.811+08 3.161+08 1.25+05 0.001+00 0.00100 9.351+07 1.511+08 6 Co-57 0,001+00 6.3619+06 L031+07 0.00+00 0.001+00 0.001+00 2.171+07 7 Co-58 0.001+00 1.891+07 4.701+07 0.001600 0.001+00 0.001+00 4.701*07 8 Co-G0 0.001+00 6.001+07 1.421+08 0.001+00 0.001+00 0.001+00 1.431+08 9 Zn-65 3.971+09 1.361+10 6,271+09 0.001+00 6.601+09 0.005+00 1.151+10 10 Rb-86 0.001+00 1.881+10 9.281+09 0.001+00 0.001+00 0.001+00 4.811+08 11 Sr-89 1.011+10 0.001+00 2.891+08 0.001+00 0.001+00 0.005+00 2.071+08 12 Sr-90 8.221+10 0,009+00 2.091+10 0.001+00 0.001+00 0.001+00 1.031+09 13 T-91 5.791+04 0.001+00 1.541+03 0.001+00 0.001+00 0.001+00 4.151+06 14 Zr-95 5.331+03 1.301+03 9.221+02 0.001+00 1.401403 0.001+00 15 Kb-95 4.871+05 2.011+05 1.161+05 0.001+00 1.441+05 0.001+00 1.691+08 16 Nb-97 2.631-11 5.621-12 2.031-12 0.001+00 4.391-12 0.001+00 1.771-06 17 0o-99 0.001+00 1.T71+08 3.451+07 0.001+00 2.641+08 0.001+00 5.831+07 18 Tc-992 2.341+01 4.821+01 6.211+02 0.001+00 5.191+02 2.521+01 1.401+04 19 h-103. 7.08103 0.001+0 2.361+03 0.001+00 1.471+04 0.001+00 8.591+04 20 h 6106 1.341+05 0.001+60 1.071+04 0.001+00 1.581+05 0.001+00 1.011+06 21 A9liOa 2.751+08 2.011+08 1.331+08 0.001+00 2,881+08 0.001+00 1.041+10 22 Sb-124W 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00 23 Sb-125 ... 0.001+00 0.001+00 0.081+00 0.001+00 0.001+00 0.001+00 0.001+00 24 TeU12Ta 3.161+08 1.051+08 3.831+07 9.141+07 7.791+08 0.001+00 1.281+08 25 Te-129a 4.581+08 1.571+08 7.069+07 1.761+08 1.151+09 0.001+00 2.741+08 26 1-131 2.311+09 2.721+09 1.201+09 8.951+11 3.18 +09 0.001+00 9.721+07 27 1-133 3.081M+07 4.491+07 1.311+07 8.171+9 5.281+07 0.009+00 7.601+06 28 Ca-134 2.511010 4.695+10 4.731+09 0.001+00 1.211+10 4.95M+09 1.271+08 29 Ce4138 1.681+09 4.935*09 1.841+09 0.001+00 1.971+09 4.021+08 7.491+07 30 Cez137 3.481+10 4.071+10 2.891+09 0.001+00 1.081+10 4.431+09 1.271+08 31 Ba-140 2.051+08 2.051+05 1.051+07 0.001+00 4.861+04 1.261+05 5.021+07 32 La-140 3.451+01 1.361+01 3.501+00 0.001+00 0.001+00 0.001+00 1.601+05 33 Ce441. 3.571+04 2.181404 2.571103 0.001+00 6.721+03 0.001+00 1.131+07* 34 Ce÷144 1.651+06 6.759+05 9.251+04 0.005+00 2.731+05 0.001+00 9.471+07 All nuclidee (except H-3) calculated: per ODCH equation 2.3-24 H-3 calculated per ODUI equation 2.3-28
- , Procedure Number: Beaver Valley Power Station P..oc-ed ....Title: Unit: Level Of Use: 1/2 In-Field Reference OD : GASEOUS EFFLUENTS Revision:
Page Number: ATTACHMENT J Page 16 of 19 P&I ORGAN DOSE FACTORS Table 2.3-17 R VALS F0R 131811V VALLEY G171 (sq mietei-ra/lr per uCi/sec)Pathway Goat Milk Age Group = Adult Iclide Bone Liver T. Body Thyroid Kidney Lung -l-LI 1 H-3 0.001400 1.561+03 1.5,1+03 1.561+03 1.561+03 1.561+03 1.561+03 2 P-32 1.741#10 1.081+09 6.721#08 0.001+00 0.001400 0.001+00 1.961+09 3 Cr-51 0.001400 0.001+00 2.M51+03 1.701+03 8.281+02 3.781+03 7.171+05 4 n-54 0.001+00 7.141+05 1.38+05 0.001+00 2.121+05 0.00140 2.191+06 5 1e-59 3.121+05 7.321+05 2.81105' 0.001+00 0.001+00 2.051+05 2.441+06 6 Co-57 0.001+60 1.096,05 L821+05 0.001+00 0.001+00 0.001+00 2.771+08 7 Co-58 0.001+00 4.401+05 9.861+05 0.001+00 0.001+00 0.001+00 8.911406 8 co-60 0.001+00 1.341+06 2.961406 0.001+00 0.001+00 0.001+00 2.521+07 9 Zn-85 1.161+08 3.741+06 1.691+08 0.001+00 2.501+08 0.001+00 2.361+08 10 1b-88 0.001+00 2.831+08 1.221+08 0.001+00 0.001+00 0.003+00 5.181+07 11 Sr-59 2.431+09 0.001+00 6.991+07 0.001+00 0.001+00 0.001+00 3.911+08 12 Sr-90 6.641+10 0.006+00 1.839140 0.001+00 0.001400 0.001400 1.929+09 13 1-91 8.141+02 0.006+00 2.181+1 0.001+00 0.001+00 0.001+00 4.481+05 14 Zr-95 8.871+01 2.851+01 1.931+01 0.001+00 4.471*01 0.001+00 9.021+04 15 lb-95 8.131+03 4.521403 2.431+03 0.001+00 4.471+03 0.001+000 2.741+07 16 lb-97 3.381-13 8.541-14 3.121-14 0.001+00 9.961-14 0.001+00 3.151-10 17 1o-99 0.001+00 2.531+06 4.811405 0.001+00 5.721406 0.001+00 5.81,+06 18 Tc-99m 3.391-01 9.591-01 1.229101 0.001+00 1.461+01 .4.701-01 5.671+02 19 ha-103 9.951+01 0.001+00 4.291+01 0.001+00 3.801+02 0.001+00 1.161+04 20 h-106 1.721+03 0.001+00 2.181402 0.001400 3.321303 0.001+00 1.111+05 21 Ag-110i 4.991+08 4.811+06 2.741+06 0.001+00 9.071+06 0.001+00:- 1.881+09 22 b-124 0.001600 0.001+00 0.006+06 0.006+00 0.00166 0.001600 0.001+00 23 Sb-125 0.001+00: 0.001+00 0.001+00 0.001+00 0.001+00 0.001+00: 0.001+00 24 Te-127m 4.139+06 1.480+08 5.031+05 1.051+06 1.681+07 0.001+00 1.381+07 25 Te-129@ 5.941406 2.221+06 9.411+05 2.041+08 2.481+07 0.001400 2.991+07 26 1-131 3.021+08 4.321+08 2.481+08 1.421+11 7.401+08 0.001+00 1.141+08 27 1-133 3.9519+06 6;87106 2.091+08 1.01109 1.203+07 0.001+00 6.171+06 28 Cs'134 4.671+08 1.111+09 9.091408 0.001+00 3.601+08 1.191+08 1.951+07 29 Ce-136 6.701+08 2.651+09 1.901+09 0.001+00 1.471+09 2.021+08. 3.011+08 30 Ce-137 1.501+10 2.051+10 1.341+10 0.001+00 6.951+09 2.311+09: 3981+08 31 Ba-140 2.741+06 3.441+03 1.791+05 0.001+00 1.171403 1.971403 5'5*641+06 32 La-140 4.801401 2.321-01 6.131:02 0.001+00 0.001+00 0.001+00, 1.701+04 33 Ce-141 4 *791024 3.241+02 3.886401 0.00140 1.511+02 0.001+00 1.241+06 34 Ce-144 3.051+04 1.271+04 1.841+03 0.001+00 7.55.1403 0.001+00' 1.031+07 All unclides (except 1-3) calculated per ODCM equation 2.3-24 H-3 calculated per ODCH equation 2.3-28 J Procedure Number: Beaver Valley Power Sitation 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:__2 107 of 130 ATTACHMENT J Page 17 of 19 P&I ORGAN DOSE FACTORS Table 2.3-18 R ORl RIUD VAULT SITE (sq seter-area/yrper uCI/e¢c)Pathway Goat il1k Age Group -Teen Nuclide Bone Liver I. Body Thyroid Kidney Lug GI-,LI 1 H-3 0.001+00 2.031+03 2.031403 2.031+03 2.034+03 2.031o03 2.031+03 2 P-32 3.211+10 1.991W09 1.241+09 0.001+00 0.001+00 2,701+09 3 Cr-51 0.001+00 0.001+00 4.961+03 2.771303 1.091403 7.111W+03 .371+05 4 In-54 0.00140 1.191+06 2.361405 0.00100 3.551+05 0.001+00' 2.441+06 5 le-59 5.441+05 1.271406 4.903+05 0.001+00 0.001400 4.001+05 3.001+06 6 Co-sT. 0.001400 1.921+05 3.211+05 0.001+00 0.001+00 0.001+00 3.571+06 7 Co-58 0.001400 7.401+05 1.711+08 0.001400 0.001400 0.001400 1.023+07 8 Co-60. 0.001+00 2.271406 5.11+06 0.001+00 0.001400. 0.001+00 2.961+07 9 Zn-65 1.811#08 "6.271+08 2.931+08 0.001.+00 4.011+06 0.001+00 2.661+08 10 1 o-86 0.001+00 4.791+08 2.251+08 0.001+00 0.001+0 0.001+00 7.091+07 11 St-89 4.491+09 0.001+00 1.291+08 0.001+00 0.001+00 0.001oo0 5.351+08 12 Sr-.90. 9.391+10 0.001600 2.321+10 0.001.90 0.001400 0.001+00 2.641+09 13 T-91 1.501+03 0.001+00 4.011+01 0.001900 0.001+00 0.001+00. 6.141+05 i4Zr-95 1.551+02 4.901+01 3.371+01 0.001+00 7.191401 0.001+00 1.131+05 15 1b-95 1.391+04 7.691+03 4.231+03 0.001+00 7.451+03 0.001400 3.291+07 16 Ib-97 6.151-13 1.531-13 5.571-14 0.001+00 1.791-13 0.001+00 3.651-09 17 Ho-99 0.001+0,0 4.561+06 8.101+05 0.001+00 1.041+07 0.001+00 8.171+06 18 Tc-99i 5.881-01 1.641+00 2.131+01 0.001+00 2.451+01 9.111-01 1.081+03 19 hn-103 1.771+02 0.001400 7.561+01 0.001+00 6.241402 0.001+00 1.481+04 20 h-106 2.441+03 0.001+00 3.981+02 0.001+00 6.101403 0.001+00 1.521+05 21 Ig-ll1a .,.241 + .801+06 4.751406 1.491+07 0.001+00 2.191409 22 Sb-124 0.001+00 0.001+00 0.001+00 0.001+00 0.001400 0.001+00 0.001+00 23 Sb.425 0.001+00 0.001+00 0.003+00 0.001+00 0.001#00 0.001+00 0.001+00 24 Te-127m 7.811+06 2.701+06 9.051+05 1.811+06 3.0810 0.001+00 1.901+07 25 Te-129u 1.091+07 4.031+06 1.721+06 3.511+06 4.551+07 0.001+00 4.081+07 26,1-131 5.481+06 7.671+08 4.121+08 2.241+11 1.321+09 0.001+00 1.521+08 271-133: 7.211+06 1.221407 3.731+06 1.711409 2.151+07 0.001+00 9.261+06 28 Ca-134:. 8.111+08 1.911+09 8.861+08 0.009+00 6.071+06 2.321+08 2.381+07 29 Co-136 1.141+09 4.491+09 3.021+09 0.009+00 2.441+49 3.851+08 3.611+08 30 Ca-137 2.711+10 3.611+10 1.261+10 0.001+00 1.231+10 4.771+09 5.141+08 31 Ba-140 4.941+06 6.061+03 3.181+05 0.001+00 2.051+03 4.071+03 7.621+06 A32 La-140 8.271-01 4.061-01 1.081-01 0.001+00 0.001+00 0.001+00 2.331+04 33 Ce-141 8.791+02 5,871+02 6.741+01 0.001+00 2.761+02 0.001+00 1.681+06 34 Ce-144 5.601+04 2.321+04 3.011+03 0.001+00 1.391+64 0.001+00 1.411+07 All nuclidea iezcept 0-3) calculated per OD equation 2.3-24 H-3 calculated per OoCa equation 2.3-28 P~rocedure Number: BeaverValleyoPwer StatiOn 1/2,ODC-2.02 Title: Unit: Level Of Use:/ I In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: S ... .2 , .1.08-of 130 ' -.ATTACHMENT J Page 18 of 19 P&I ORGAN DOSE FACTORS Table 2.3-19! VAWIS JOR 31A11R VALLIT SIT[(sq seter-ares/rr per oCI/aec)Pathbay Goat Milk Age Group : Child kcl~ide Bone Liver T. Body Thyroid Ildney Lug, GI-LLI I E-3 0.001+00 3.201+03 3.201403 3.201+03 3.201+03 3.201+03 3.201+03 2 P-32 7.9.l+I40 3.701+09 3.051409 0.001+00 0.001600 0.001+00 2.191+09 3 Cr-51 0.001+00 0.001+00 1.021+04 5.641+03 1.541+03 1.031+04 5.391+05 4 Mn*54 0.001+00 1.781+06 4.741405 0.001+00 4.991+05 0.001+00 1.491+06 5 ye 59 1.261406 2.041+06 1.021406 0.001+00 0.001+o00 5.911+05 2.121+06 ,6 Co-57 0.001+00 3.271+05 6831+05 0.001+00 0.001+00 0.001400 2.681+06 7 Co-$$ 0.001+00 1.131+0 3.461+06 0.001+00 0.001400 0.001+00 8 Co-80 0.001+00 3.531+06 1.041+07 0.001+00 0.001+00 0.001400 1.951407.3.541+06 9.441*08 5.871308 .0.001+00 5.951+08 0.001+00 1.661+09 '9 ?10 Rb-86 0. 00z+00 9.881+00 5.4 161+08 0.001+00 0.001+00 0.001+00 5.711407 11 Sr-89 1.111+10 0,001+00 3.171#08 0.001+00 0.001+00 0.001+00 4.301+08 12 Srg90 1.591+11 0.001400 4.021*10 0.001+00 0.001400 0.001+00 2.141+09 13 Y-91 3.701+03 0.001+00 9.893+01 0.001+00 '0.001+00 0.001600. 4.931+05 14 Zr-95 3.601+02 7.921+01 7.051+01 0.001+00 1.133602 0.001+00 8.271+04 15 lb-95 3.131+04 1.221+04 8.711+03 0.001+00 1.141+04 0.001+00 2.251+07 16 lib-97 1.491-12 2.701-13 1.261-13 0.001+00 2.991-13 0.001+00 8.331-08 17 No-99 0.001+00 .8.301+06 2.051+06 0.001+00 1.771+07 0.001+00 6.871+06 18 Tc-99a 1.353+00 2.651+00 4.391401 0.001400 3.841+01 1.341+00 1.511+03 19 --1OS 4.181+02 0.001+00 1.611+02 0.001+00 1.051+03 0.001+00 1.081+04 20 lu-106 7.791403 0.001+00 9.723+02 0.0013+00 1.051+04 0.001300 1.211+05 21 Ag-llOn 1.791+07 1.211+07 9.653#06 0,001+00 2.251+07 0.001+00 1.441+09 22 Sb-124 0.001+00. 0.001+00 0.001+00 0.001400 0.00100 0.00.+00/ 0.001+00 23 Sb-125 0.001+00, 0.001+00 0.01*00 0.001+00 0.003+00 0.001+00 0.001÷00 24 Te-127a 1.881+07. 5.051+06 2.231406 4.481406 5.351+07 0.001+00. 1.521+07 25 Te-129- 2.681+07 7.481+06 4.161+06 8.641+06 7.871+07 0.001+00. '3.211+07 26 1-131 1.331+09 1.341+089 7.01+08 4.421+11 2.191409 0.001*00 1.191+08 27 1-133 .1.751+07 2.171+07 8.201306 4.031+09 3.611+07 .0.001+00: 8.731+06 28 Ca-134 1.811+09 3.071+09 8.481+08 0.001+00 9.521+06 3.421+08 1.661+07 29 Ca-I36 2.581409 7.081+09 4.581+09 0.001+00 :3.771+09 5.621+08.: 2.491+08 30 Ca-137 6.543+10 6.286+10 9.241+09 0.001+00 2.041+10 7.341+09 3.921408 31 Ba-140 1.191+01 1.051+06 6.961+05 0.001+00 3.401043 6.231+03 6.041M00 32 La-140 1.981400 6.921-01 2.331-01 0.001+00 0.001+00 *0.001+00 1.931+04 33 Ce-141 2.161403 1,081+03 1.601303 0.001+00 4.731+02 0.001+00. 1.351+*8 34 Ce-144 1.381+05 4,331+04 7.371+03 0.001+00. 0.001+00 1,131+01 All nuclidea (except 1-3) calculated per 0(] equation 2.3-24 8-3 calculated per 01D equation 2.3-28 Beaver Valley Power Station Procee Number:-......1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 109 of" 130 ATTACHMENT J Page 19 of 19 P&I ORGAN DOSE FACTORS Table 2.3-20 R VAILME FOR BEAVER VALLIT SITE (sq seter-areh/yr per uCi/sc)Pathway Goat milk Age Group : Infant Euclide Boae Liver T. Body Thyroid Kidney Lung GI-LLI 1 1-3 0.001+00 4.81*403 4.866103 4.881*03 4.861403 4.881*03 4.861+03 2 P-32 1.631+11 9.591+09 6.321+09 0.001+00 0.001+00 0.001400 2.211*09 3 Cr-51 0.001+00 0.001400 1.611404 1.081+04 2.291403 2.04+04 4.691+05 4 KN-54 0.0010+0 3.311+06 7.601+05 0.001+00 7.331*05 0.001*00 1.211+06 5 e-59 2.351,08 4.111+06 1.621+06 0.001+00 0.001+00 1.211406 1.981,06& Co-57 0.001+00 7.641+05 1..241*0 0.001+*00 0.001+00 0.001+00 2.601+06 7Co-58 0.001+00 2.261*068 5.641+08 0.0010+0 0.001*00 0.001*00 5.641+06 8 Co-0 0,001400 7.201*08 1.701*07 0.001*00 0.00140 0.001+00 1.715*07 9 Zn-65 4.761+08 1.631+09 7.531+08 0.001+00 7.921096 0.001*00 1.380109.10 lb-80 0.001*00 2.251+09 1.111+09 .0.001*00 0.001*00 0.001+00 5.771+07 11 Sr-89 2.111+10 0.001*00 6.061+08 0.001+00 0.001+00 0.001+00 4.341+08 12 Sr-90 1.731+11 0.001+00 4.391+10 0.001+00 0.0010*0 0.001+00 2.168109 13 Y-91 6.941+03 0.001+00' 1.851*02 0.001*00 0.001+00 0.001400 4.981+05 14ka-95 6.401+02 1.561+02 1.111*02 0.001*00 1.681*02 0.001*00 7.771+04 15 lb-95 5.841*04 2.411+04 1.391+04 0.001*00 1.721*04 0.001*00 2.031*07 16 Kb-97 3.181-12 6.741-13 2.431-13 0.001+00 5.271-13 0.001+00 2.131-07 17 No-99 0.001*00 2.121*07 4.141+06 0.0010*0 3.171*07 0.001+00 6.991*06 N Tc-99v 2.611*00 5.791+00, 7.486101 0.01+00 6.231*01 3.031*00 1.681*03 19 Ru-103 8.471+02 0.001*00 2.831+02 0.001*00 1.768103 0.001*00 1.031*04 20.-.106 1.6019+04 .0.00100 2.001+03 0.001+00 1.901*04 0.001*00 1.221#05 21 Ag-110 3.301*07 2.411*07 1.601+07 0.001+00 3.451+07 0.001+00 1.251409 22 Sb-124 0.001+00 0.001l00.: 0001l00 O.001*+0 0.001+00 0.001400 0.001*00 23 Sb-125 0.001+00 0.001*00 0.001+00 0.001*00 0.001+00 0.001*00 0.001+00 24 Toe-127a+ 3.801*07 1261.407 4.591*06 1.101+07 9.351+07 0.001*00 1.539407 251le-129. 5.501+07 1.891*07. 8.471*08 2.111+07 1.381*08 0.001100 3.281*07 261-131 2.771409 3.271+09 1.441+09 1.071+12 3.821+OS 0.001+00 1.171+08 27 1-133 3.701*07 5.391+07 1.586107 9.801*09 6.341*07 0.001+00 9.121+06 28 Ca-134 3.021+09 5,621+0S 5.688+08 0.001+00 1.451*09 5.931*08 1.531+07 29 Ca-138 5.031*09 .148+10. 5.521*09 0.001+00 5.901*09 1.211409 2.251+08 30 Ca-137 1.041+11 1.221+11 8.661+09 0.001+00 3.261+10 1.331+10 3.821*08 31 Ba-140 2.45107 2.453+04 1.268106 0.001400 5.831*03 1.511*04 6.031*06 32 La-140 4.141+00 1.631+00 ' 4191-01 0.001*00 0.0010+0 0.001+00 1.921+04 33 Ce-141 4.291*03. 2.821*03. 3.081+02 0.001*00 0.071*02 0.001*00 1.353106 34 Ce-144 1.981*05 8.11*#04 1.111+04 0.001+00 3,281+04 0.001+00 1.141*07 All nuclides (except 8-3) calculated per O)1W equation 2.3-24 0-3 calculated per ODC0 equation 2.3-28 Procedure Number.-Beaver Valley Power Station 1 /2- ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: , 2 110 of 130 ATTACHMENT K Page 1 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)--I 000 c 00C M0 00000 00 n000 0\O O00 r- C-4 aO G M%0* 0 -N a -r- oo-o 0cv 0 rn ---r--a\~ 0en00 0n% \ p00 0000 00 00 < 10 0 n W1O cý"-v 1.0OO r-W Te C4 NC1- CA C 0 00 000 0 0 C 0 Q-- 0 W -00a\--.-ooooo %0 0N000 00000 0 4 Lz.ýI W; 4 Vý c A 0\,aý 0NO.O' 0 0<D000 0 0 000---o .0 0 0 ý" c
- J k)'T ': , .0 N a. , ý qN aý aý 0 0 0 0 <D '0 CD*I~ : .~ .... OO p CýC c) O c M -0 O'.\4 ýO\OO 0 %~O 0'M -- e ZS --(D en 'I o 0-9 CD-L=0ýz ~ ~ l -> 0. C>0.~* -** o 99oq0*e9-C 0 W 4 44,Lh4 OWQ W W WW* 00 00cq r c0 .00'00 Q0-I--n-c4
- 0 1,'/ .000.1 O\O'ý 0 O\O4 Oen000 O\0 000" r* ý en0 10 0 'T 4- 00 W000 0----0 I 00 U 1 0w 'IT r- W) 00k N )4nc alW)0 tt 0%a 0 C ,6 4Z -4~L C/c/ ti , -i4 4 Procedure Number:;Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
Page Number:-2 Ill of 130 ATTACHMENT K Page 2 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)000 00 CA \O~Clý0 C4e-~On O 0 OOON,-7-0 00 )00 enro 0,C 0ON en 0= nd 0NýNO---------------------------------------- 0000 lz .C1400 C..)z 0..)0 I-]z 0 C-)00 4 C*00 00 C%0 C?00 00 W W 00N a, 9 (0 Cl 00 N 00 0 Cq 99 00" 00 00 00 00 in cin aN 9 C:1 kn 00 (ON ON4 Clý00 In"7 C~l Cli 00o ON\Ol 0 Cl Lý9 C1l'.0 ON vI 00 Clz 00 Cli 0000 0zr00 00 Iný 00 0 0'N 0 0 0 0 ON 9 O'N ONOC 07,00 000 9 9~~'Cl\0 ON 0 00 90 0ON-0 0C t"0" 0%CD 0\00 0 C14 0ý0 0 Cý00 06c~l 0 In 0 00 0 Cl q0 0, ON 0 a)Cl In'I?00 0 a)'~0 Cl 00 9>)0 00 0 9)ON 00 9)00 0 Cn'00 0 Wi ON IT 0 I-W-En.Wi. WI W W .)W Z W# LI) V)zZ Li)WW ciV) ))V)V z .Procedure Number: Beaver Valley Power Station : /2-ODC-2.02 Title: Unit: Level Of Use: 1/2 IIn-Field Reference ODCM: GASEOUS EFFLUENTS Revision:ePage Number: 2 112 of130 ATTACHMENT K Page 3 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)TABLE 2.3-23 VV-1 AND VV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR>150 HRS/QTR (meters 2)Same as Table 2.3-22 Procedure Number: Beeaver Valley Power Station 1/2-0DC-2.02 Title: Unit: Level Of Use: 12 I In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:-1 2 113 of 130 ATTACHMENT K Page 4 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES))TABLE 2.3-24 TV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR > 150 HRS/QTR (meters-2) Same as Table2.3-22 r i Title: ODCM: GASEOUS EFFLUENTS ATTACHMENT K Page 5,of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)TABLE 2.3-25 CB-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR > 150 HRS/QTR (meters"2) Same as.Table 2.3-22 pO Procedure Number: Power Station 1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 115 of 130 ATTACHMENT K" Page 6 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)TABLE 2.3-26 DV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters 2)Same as Table 2.3-22 Beaver Valley Power Station. P.ocedure Number11 )C-2.0 2 Title: Unit: [Level Of Use 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: P Number: V__ 2 "_"116_of_130_"_" ATTACHMENT K Page 7 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)TABLE 2.3-27 WV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters 2)Same as Table 2.3-22"Ai Beaver* Valley Power Station Procedure NumberODC 2 2 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 117of130 ATTACHMENT L Page 1 of7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-28 PV-1/2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR > 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)(1 E-9 meters-2)INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N NNE NE ENE E ESE SE SSE S SSW SW WSW W VWNW NW NNW.600.673.766 1.010 1.370.984 11.000 7.060'5.780 2.040 1.610 1.710.377.424.447.340 2.340 3.220 1.280 5.080 4.420 6.390 3.680 3.220 1.540 1.040 1.120 1.310.659.746.425 1.840.660.401.466.423 1.410.578.370.138.497.572.524.111.702 1.290 2.340.466.105.208.693.029.070.043.707 2.920.660 1.290 6.390 1.300 3.140 2.610 1.040.979 1.190.518.746.488.545 2.510 3.220 1.200 1.760 4.420 6.A80 3.680 4.320 2.730 1.460 1.120 1.310.659.746.422 1.92 -Procedure Number: Beaver Valley Power Station_ _ _ _ _ _ __ -1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision.: Page Number: S2" 118 of 130'ATTACHMENT L Page 2 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-29 CV-1 AND CV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR >150'HRS/QTR FORSPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)(1 E-9 meters")INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN. COW GOAT ANIMAL RESIDENCE N 25.40 2.05 -" .693 .847 2.19 NNE 18.80 2.02 -- .459 1.850 2.11 NE 63.40 29.30 .455 .078 .455 30.40 ENE 65.90 8.92 -- .661 32.20 E 38.00 3.90 .382 1.020 1.020 22.70 ESE 17.10 3.56 -- 1.380 3.560 3.56 SE 13.80 3.03 .350 .350 1.100 3.03 SSE 10.50 2.65 .317 .094 2.570 3.68 S 10.60 1.05 .934 -- 1.860 1.95 SSW 5.59 1.26 .663 .266 1.260 4.42 SW 3.94 2.21 -- 1.320 1.920 2.21 WSW 27.50 2.65 .596 -- 2.380 2.65 W 31.60 1.23 .645 -- .960 1.23 WNW 39.10 2.23 1.490 .045 2.230 2.23 NW 70.60 15.00 -- .276 1.990 15.60 NNW 31.50 6.52 .068 1.090 .9.91 Procedure Number: BeaverValley Power. Station __oo ____________ ___ ___ ___ ___ ___ ___ ____ ___ ___ ___ ___ ___ ___1/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 119of 130 ATTACHMENT L Page 3 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-30 VV-1 AND VV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIEDIN ATTACHMENT E TABLE 2.2-3)0( E-9 meters"2).:Same as Table 2.3-29 Is Beaver Valley Power Station Procedure Numb c 2 , 0 2 Title: Unit: I Level Of Use: J S I In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:
- .[PageNumrber:
.... 2, 1_ 11( "1111)ATTACHMENT L Page 4 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-31 TV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR>150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2,.2-3)(1E-9 mheterS" 2)1W INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 20.20 34.90 54.20 57.50 38.10 18.60 19.00 13.30 11.30 6.44 3.95 25.10 28.40 30.90 56.10 25.10 2.05 2.02 29.30 8.92 3.90 3.56 3.03 2.65 10.40 1.26 2.21 2.65 1.23 2.23 14.90 6.53.455.382.351.318.934.664.597.646 1.490.693.459.078.661 1.020 1.380.351.094.266 1.320.045.276.068.847 1.850.455 1.020 3.560 1.100 2.570 1.860 1.260 1.920 2.380.961 2.230 1.980 1.100 2.190 2.110 30.400 32.200 22.700 3.560 3.030 3.690 1.950 4.430 2.210 2.650 1.230 2.230 15.500 9.920 p I Procedure Number: Beaver Valley Power Station , , .. + ' ' 1/2-ODC-2.02 Title: ... ....Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: 1 2 121 of 130 ATTACHMENT L Page 5 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE -2.3-32 7 CB-2 D.EPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT ETABLE 2.2-3)(1E-9 meters-2)Same as Table 2.3-31 Procedure Number: Beaver "1/2-ODC-2.02 Title: Unit: Level Of Use:-1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision:% Page Number:.)2 of 1.30 ATTACHMENT L Page 6 -of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-33 DV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)(1E-9 meters')Same as Table 2.3-29)f Beaver Valley Power Station Procedure Numb/2OC2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:__2 123 of 130 ATTACHMENT L Page 7 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-34 WV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES:>500 HRS/YR OR >150:HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN- ATTACHMENT: E TABLE 2.2-3)(I E-9 meters-2)Same as Table 2.3-29 Procedure Number: Beaver Valley Power Station Unit i/2-0DC-2.02 Title: Unit: Level Of Use: 1/2 [ In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: PageNumber:. _ _I _ _2 .-1 , 124,of 1130.ATTACHMENT M Page 1 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-35 CV-1 AND CV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES_>500 HRS/YR OR 150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)S(sec/mr 3)INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR* BOUNDARY GARDEN COW GOAT ANIMAL RESIDENCE)N NNE NE ENE E ESE SE SSE S SSW SW WSW 8.2 1E-5 3.04E-5 4.59E-5 3.72E-5 2.93E-5 2.47E-5 2.14E-5 2.2 1E-5 2.15E-5 2.18E-5 1.82E-5 1.09E-4 1.49E-4 1.91E-4 3.08E-4 1.80E-4 8.38E-6 4.71E-6 2.2 1E-5 5.25E-6 3.79E-6 5.61E-6 5.OOE-6 6.3 1E-6 3.03E-6 6.58E-6 1.03E-5 1.29E-5 1.05E-5 1.72E-5 6.13E-5 3.54E-5-- 3.72E-6-- 1.40E-6 6.05E-7 1.38E-7-- 5.66E-7 5.15E-7 8.13E-7 1.11 E-6 2.76E-6 3.8 1E-6 4. 1OE-6 1.17E-6 2.34E-6 8.13E-7 3.92E-7 1.82E-6 6.67E-6 4.34E-6 4.38E-6 6.05E-7 1.17E-6 5.61E-6 2.03E-6 6.13E-6 4.93E-6 6.58E-6 9.12E-6 1.19E-5 8.77E-6 1.72E-5 1.36E-5 9.27E-6 8.82E-6 4.87E-6 2.28E-5 1.88E-5 1.78E-5 5.61E-6 5.OOE-6 8.49E-6 5.14E-6 1.78E-5 1.03E-5 1.29E-5 1.05E-5 1 .72E-5 6.36E-5 5.29E-5 p W WNW NW NNW 6.55E-6 --1.28E-5 1.231E-6-- 3.80E-6-- 1.35E-6 Measured relevant to center point between BV-I and BV-2 Containment Buildings Period of Record: 1976 -1980.LP Procedure Number: Bea'ver Valley Power Station l/2-ODC-2.02 Title: Unit: Level Of Use: 1/2 In-Field Reference ODCM: GASEOUS EFFLUENTs Revision: Page Number:..... 2 125 of 130 ATTACHMENT M Page 2 of 3.BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-36 VV-1 AND VV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES>500 HRS/YR OR >I50,HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)(sec/m 3)INDIVIDUAL RECEPTORS DOWNWIND SITE VEGETABLE MILK MILIK MEAT SECTOR* BOUNDARY GARDEN COW: GOAT ANIMAL RESIDENCE N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW 3.NW NNW 9.75E-5 3.78E-5 6.13E-5 4.83E-5 3.66E-5 2.99E-5 2.55E-5 2.65E-5 2.52E-5 2.60E-5 2.13E-5 1.34E-4 1.77E-4 2.33E-4 3.32E-4 1.90E-4 1.00E-5 5.11E-6 2.70E-5 5.58E-6 3.99E-6 6.13E-6 5.29E-6 6.72E-6 3.14E-6 7.34E-6 1.18E-5 1.51E-5 1.25E-5 2.07E-5 8.57E-5 4.69E-5 6.20E-7 5.25E-7 8.24'E-7 1. 12E-6 4.21E-6 1.43E-6 1.40E-7 5.7 1E-7 1.19E-6 2.43E-6 8.24E-7 3.95E-7 4.95E-6 4.72E-6 6.20E-7 1.19E-6 6.13E-6 2.13E-6 6.53E-6 5.29E-6 7.34E-6 1.04E-5 1.38E-5 1.02E-5 2.07E-5 1.64E-5 1.09E-5 1.06E-5 5.30E-6 2.8 1E-5 2.24E-5 2. 1OE-5 6.13E-6 5.29E-6 9.22E-6 5.53E-6 2.09E-5 1.18E-5 1.51E-5 1.25E-5 2.07E-5 8.85E-5 6.75E-5 2.83E-6 --4.15E-6 1.92E-6-- 7.41E-6 4.46E-6 --7.40E-6 1.49E-5 1.30E-6 4.24E-6 1.45E-6*Measured relevant to center point between BV-I and BV-2 Containment Buildings Period of Record: 1976 -1980 Procedure Number." Beaver Valley Power Station .... 17:D-20 Title: ODCM: GASEOUS EFFLUENTS Unit: Level Of Use: 1/2 In-Field Reference Revision: Page Number: 2 126 o<f'l 1.ATTACHMENT M Page 3 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES) TABLE 2.3-37 PV-1/2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES>500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)(sec/m 3)INDIVIDUAL RECEPTORS a DOWNWIND SITE VEGETABLE MILK MILK MEAT SECTOR* BOUNDARY GARDEN COW GOAT. ANIMAL RESIDENCE N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NNWý,NNW 3.09E-9 2.85E-9 2.02E-10 1.02E-9 2.15E-9 6.90E-9 2.91E-6 4.9 1E-6 2.4 1E-6 4.83E-6 4.82E-6 5.77E-7 2.88E-9 3.40E-9 1.34E-9 I1.52E-9 3.30E-6 2.68E-6 7.42E-9 3.2 1E-6 2.91E-6 4.97E-6 3.52E-6 3.56E-6 1.78E-6 2.52E-6 2.75E-6 2.8 1E-6 1.68E-6 1.61E-6 3.3 1E-8 3.73E-6 5.44E-7 1.13E-6 6.52E-7 1.24E-7 6.29E-7 4.96E-7 1.14E-6-- 1.95E-6 6.02E-7 6.02E-7 6.53E-7 2.18E-7 1.34E-6 2.47E-6 5.44E-7 1.14E-6 4.97E-6 1 43E-6 3.47E-6 2.84E-6 2.52E-6 2.44E-6 2.57E-6 1.37E-6 w 1.61E-6 I .07E-6 1.31E-6 3.36E-6 2.68E-6 5.51 E-9 1.67E-9 2.91E-6 4.8 1E-6 3.52E-6 4.71E-6 2.96E-6 3196E-6 2.75E-6 2.8 1E-6 1.68E-6 1.61 E-6 3. 1OE-8 3181E-6'p K.1.65E-6 1.50E-6 8.79E-7 4.89E-7 1.131E-6 6.60E-7 1.78E-6 1.1OE-7, 2.03E-7 1.73E-7*Measured relevant to BY-I natural draft cooling tower Period of Record: 1976 -1980 I..) Procedure Number: Beaver ValleyPoeSti12bC.0 Ttl Po er taton1/2-ODC-2.02 Title: Unit: Level Of Use: 1./2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number:.,,,2 127of 13-0 ATTACHMENT N Page 1 of 1 BATCH RELEASE DISPERSION PARAMETERS (0 -5 MILES)00 Cl O 0-Q~Al z 0 U S C.4)z 0 0 z 0 U U z C,)0*0 0 e4 ci 0 C14 N N N'.0-Cl 000~~N'/N ~ '/N Cfl Oý oý l'I n e-N L Cl N 0 04 N N N N'IN tIN N '.0 N N N N-'.o ~-'IN N Cl N'.0'.ON-riN Ci 0'.'CN 'T e NNNN Cl ON ON N '.0 00 ON co00 C9 N-00 "l'~e N N Clc~N N N N ON 00 N Cl'(N r-z N'.0 0 oR 00 .~aC1 00 t. a 4 fN 00 N 00 00 NNN O Nt W/N N r-Nh tfN 00 tn 06 ° 0ýen ON On c~ONeI*N 7. ",. Ceq C,-4 N~'0 .0 ON .,'.0 Cl'.0 ,~j.M N00 C~l OIT ON On'.0'0'.-0','..t~N '.0'0'.'.,'.,'., tN00-aN 00 t.n n'IT C4~00O'.0 0'.0'.0'.0 ON Cl Cl So C-!\.0 Lý00 C!00'p, 0 CD'.0'.0 0a'.0 a, N- No 0' 0 O\ ON \.0'.0 'IN 'C N Cl '4i"¢, O.. Cli'IN 0 0 I/N 0'IN 0 0 0'.0 0'/N N 0'.0 L N N Cl'.0 0'IN 00'.0'.0.00 Cn r'00 ,,en O n 00 \0 CC.Zn'0'0.'.0 00 00 '.0~t'N00 e~ný000 00 %.0 C4 It 00 N00'0 N SCl '. ON WIN ON Cl 4 CA N) K00 'IN,Cli 'IN3 ,-I/N rJ:~Cl ON Cl4 00 L'.0 oR 00 0'I U w, z z z w w w C/)C, Procedure Number: Beaver Valley Power Station, I Title: Unit: Level Of Use: 12In-Field Reference ,t ODCM: GASEOUS EFFLUENTS Revision: Page Number: 2 1'7g 2R of lo m ATTACHMENT 0 Page 1 of 1 GASEOUS RADWASTE SYSTEM FIGURE 2.4-1 BV-i AND 2 GASEOUS RADVASTE SYSTEM 7F, pD/: I: 'p Beaver Valley Power Station 1/erODC 2 O 2 Title: Unit: Level Of Use: S1/2 In-Field Reference ODCM: GASEOUS EFFLUENTS Revision: Page Number: ,; 2 129 of 130 ATTACHMENT P Page 1 of 1 BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS FIGURE 2.4-2 BV-I AND 2 GASEOUS EFFLUENT RELEASE POINTS Ohio : Kvr'ill eINme Point & Description Elevatlon N 1. Utit 1: Ventilation Vent 79 feet .24 inters 2. Unit I: ConteorIent / SLCIS Vent 154 feet -47 neters 3. Unit l;: Process Vent 475 feet -145 ters 4. Unit 2: Ventltaton Vent 85 feet I I6 aeters 5. Unit Z: Contairueent I SLCZS Vent 154 feet
- 47 mtears 6. Unit 2: Condensate Polishing Building Vent 60 feet -24 =tars 7. Unit 2: Waste Gas Storage Vault Vent 80 feet
- 24 waters 8. unit Z: Peconteminetion Bultding Vent 80 feet 24 meters 9. Unit 21 Turbine Wuiding Vent 109 feet -. 33 Moters Mote: The R# too" Point showm for the Unit 2 Turbine Building Vent Is a representative exhaust point for the 10 roof exhaust outlets.
Valley.Station Procedure Number: Beaver Valley Power Station .1/2-ODC-202 Til:Unit: ILevel Of Use: Title: 2 In-Field Reference Revision: , Page Number: ODCM: GASEOUS EFFLUENTS Rvi: P Number: ATTACHMENT Q Page 1, of I SITE BOUNDARY FOR.GASEOUS:EFFLUENTS Figure 5-1 RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.03 ODCM: Radiological Environmental Monitoring Program Document Owner Manager, Nuclear Environmental and Chemistry Revision Number I Level Of Use General Skill Reference Safety Related Procedure Yes Beaver Valley Power Station ProeOrC-umer 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference, Revision: Page Number: I 2 of23 TABLE OF CONTENTS 1.0 PURPOSE ......................................................................................................................................... 3 2.0 SCOPE .............................................................. 3
3.0 REFERENCES
AND COMMITMENTS ....................................... 3 3.1 References .............................................................................................................................. 3 3.3 Comm itments ......................................................................................................................... 4 4.0 RECORDS AND FORM S .......................................................................................................... 4 4.1 Records .................................. ................................................................................................. 4 4.2 Form s ...................................................................................................................................... 4 5.0 PRECAUTIONS AND LIM ITATIONS ...................................................................................... 4 6.0 ACCEPTANCE CRITERIA ......................................................................................................... 4 7.0 PRE RE QUISITES ............................................................................................................................ 4 8.0 PROCEDURE .................................................................................................................................. 4 8.1 REM P Overview ............................................................................................ ........................ 4 8.2 Sampling and Analysis Program ........................................................................................ 5 8.3 Crosscheck Program ....................................................................................................... 5 8.4 Land Use Census Program .................................................................................................. 6 8.5 Direct Radiation M onitoring Program ............................................................................... 7 ATTACHMENT A ..................... EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS" , ATTACHM ENT B .................................................................. LOCATION OF SAM PLIN G SITES ai
- a 11".Beaver Valley Power Station ProceureNomber:
1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 3 of 23 1.0 PURPOSE 1.1 This procedure provides the Radiological Environmental Monitoring Program (REMP)requirements from the Radiological Branch Technical Position.O 31.1.1 Prior to issuance of this procedure, these items were located in Section 3 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 Radiological
Branch Technical Position, Revision 1, 1979.3.1.2 Regulatory Guide 1.109, Calculation of Annual Dose to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, 1977.3.1.3 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1).3.1.4 Regulatory Guide 1. 111, Methods For Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977.3.1.5 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.6 1/2-ADM-0100, Procedure Writers Guide 3.1.7 1/2-ADM-0101, Review and Approval of Documents 3.1.8 CR04-00149, Radiation Protection Performance Committee Actions Items. CA- 12 required obtaining GPS satellite data for use in the REMP.3.1.9 CR05-01169, Chemistry Action Plan for transition of RETS, REMP and ODCM.CA-17, revise procedure 1/2-ODC-2.03 to convert Radiation Protection responsibilities toNuclear Environmental and Chemistry. 3.1.10 CR05-01390, Include GPS data in 2004 REMP Report and related 1/2-ODC and 1/2-ENV procedures. CA-02, revise ODCM procedure 1/2-ODC-2.03 to include an update of REMP sample locations (using the GPS Satellite data). Procedure Number: Beaver Valley Power Station o /2-ODC-2.03 Title: Unit: Ievel Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 GeneralSkill Reference Revision: Page Number: ( ,.1 4 of 0" ;3.2 Commitments 3.2.1 10 CFR 50 Appendix I 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 The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories.
6.0 ACCEPTANCE
CRITERIA 6.1 Any change 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 setpoint calculation. 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3'6)and 1/2-ADM-1640(3l.). 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0 101(3.1.7) and 1/2-ADM-1640(3'1.5).
7.0 PREREQUISITES
7.1 The user of this procedure shall be familiar with ODCM structure and format.8.0 PROCEDURE 8.1 REMP Overview 8.1.1 Attachment A, Table 3.0-1 contains the site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis frequency for various exposure pathways in the vicinity of the Beaver. Valley Power Station for the V REMP. Attachment B, Figures 3.0-1 through 3.0-6 show the location of the various sampling points. Beaver Valley Power Station ProcedureNumber: 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 5 of 23 8.2 Sampling and Analysis Program 8.2.1 Environmental samples shall be collected and analyzed according to Attachment A, Table 3.0-1. Analytical techniques used shall be such that the detection capabilities in 1/2-ODC-3.03, Table 4.12-1 are achieved.8.2.2 The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.8.2.2.1 The specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. 8.2.2.2 The initial radiological environmental monitoring program should be conducted for the first 3 years of commercial operation (or other period corresponding to a maximum bumup in the initial core cycle). Following this period, program changes may be proposed'based on operational experience.
8.2.3 Deviations
are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.8.2.3.1 IF specimens are unobtainable due to sampling equipment malfunction, THEN every effort shall be made to complete corrective action prior to the end of the next sampling period.8.2.3.2 All deviations from the sampling schedule shall be documented in the annual REMP report.8.3 Crosscheck Program 8.3.1 The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program.8.3.1.1 This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. Beaver Valley Power Station ProcedureNombr: ____ ___ ___ ___ ___ ____ ___ ___ ___ ___ i/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference, Revision: Page Number: 1 6 of 23 ..8.3.1.2 The results of analysis of these crosscheck samples shall be included in the annual REMP report. The participants in the crosscheck program may provide their program code so that the NRC can review the participant data directly in lieu of submission in the annual REMP report.8.3.1.3 IF the results of a determination in the crosscheck program are outside the specified control limits, THEN the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annualREMP report.8.3.2 TVle requirement for the participation in the crosscheck program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.8.4 Land Use Census Program 8.4.1 A census shall be conducted annually during the growing season to determine the location of the nearest milk animal, and nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).8.4.1.1 For elevated releases as defined in Regulatory Guide 1.111(3. 14), the census shall also identify the locations of all milk animals, and gardens greater than 50 square meters producing broad leaf vegetation out to a distance of 5 km (3 miles) for each radial sector.8.4.1.2 IF it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in ODCM dose calculations, THEN a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director-of the NRC Regional Office) within 30 days identifying the new location (distance and direction). 8.4.1.2.1 Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable. 8.4.1.3 The sampling location (excluding the control sample location) having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location.8.4.1.4 The results of the land-use census shall be reported in the annual REMP report. Beaver Valley Power Station Procedure Number Tite:1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program , 1/ General Skill Reference Revision: Page Number: 1 7 of 23 8.4.1.5 The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50(321) to "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation contaminated by airborne radioiodine is a major potential source of exposure. Samples from milk animals are considered a better indicator of radioiodine in the environment than vegetation. 8.4.1.5.1 IF the census reveals milk animals are not present or are unavailable for sampling, THEN vegetation must be sampled.8.4.1.6 The 50 square meter garden, considering 20% used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/mi, will produce the 26 kg/yr assumed in Regulatory Guide 1.109(3.1.2), for child consumption of leafy vegetation.
8.5 Direct
Radiation Monitoring Program 8.5.1 The increase in the number of direct radiation stations is to better characterize the individual exposure (mrem) and population exposure (man-rem) in accordance with Criterion 64 -monitoring radioactivity releases, of 10 CFR Part 50, Appendix A. The NRC will place a similar amount of stations in the area between the two rings designated in 1/2-ODC-3.03, Table 3.12-1.-END - Beaver Valley Power Station Procedure Number: 2.03 Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use:*1/2 General Skill Reference, Revision: Page Number: 1*'1 1 Rnf ?I ATTACHMENT A Page 1 of 4 EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS w 0)E 0 '4 05 0 x~ i 40) .'4~: rzi U40 C6 .U .0i 4 0 0q 0 0 U w dZ coýU0 CA 0 Vi S0-00 ( n 0C IT ITt- N t-f rn "T -'t1 0 0 0ý0 0 0= U c.4 >0 U U AA 0.. 0 ---4)-o <U)r~~a a-07ý Ml k'I 0 -Ml W) CIS N ON 00 w0 00 C. -'0 0 (N Cl '.0 It r-00( -(N (NIT '4* Q0 (N FD'.--~t r-~ -Cl ~--- -0Cl,~r-000\0(N --- -(N (N (N Cl Cl V'. in 1.0 1.0 t- 00-0' 0 0 CIS~I-U C (N z 0 Procedure Number: Beaver Valley Power Station o 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 9 of 23 ATTACHMENT A Page 2 of 4 EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS U-z 0 z 0 I-0~0*0 E C 0IQz U E'0.cH Ha H 0~o on 0, OQCI0 0 0 0g ,a 00 C7, 0 C)0 -0.9 C: 00005 0 I U ~ ~ 0 00 0(U/ j It- o'o U C)*0 Cd U-C 0~0r..W( 001100 lC 0'IT 'I0T0sr N~cl;Cý 6 4 cl;Wi -i r- O\ a, %0' %n M~ W0 't 1 N 0D a, N ~O o0Oo r Dt-r o60- -,6 4 o6 'tr %6 N- cl 4 i r-4C O M N C- cl e~~O~0N00 0-Cl ~rIV~"0ClCl "0000 HZ M" N00O O -Cl ~ S/C "0 N 00 0~ 0- Cl 00 00 00 0000 00 00 00 00 00 0\ O~ O\Cf)'IT V (71 al 42 z-0 C-i Beaver Valley Power Station IProedur 1Number: .....Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use: 1/2 General Skill Reference Revision: Page Number: 1 1 10nf23*1 ATTACHMENT A Page 3 of 4 EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS 0 r-U, , U,ý0) 0>..4-~~ Cjs .. a)0 F E U , g 0-V))C E U, CO c0-o.~0 4!."'l OX I Q(L 0 0m U 0 I~u.2 Cý.Cn U0 C)a Q C.0 U C U CIO 0~0)I-.-~ a)a)CO.~ >*~CO CA.L)CO 0~*C 0 COS 0)0'a)I-0)0 0 z 4 A to r. a)0 =)15a)0 4. U C O a) o>a)CA.2 C.'4-(1l M o00 t- 0 00-Cl! I C'4 0D '0 C en i : : C~l Cl 9 z t-a)a/)0 0 W)r W W \00 z 0 U, 0>C-)a01 i I i 71 Beaver Valley Power Station ProcdureNubODC 2 3 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program ,1/2 General Skill Reference Revision: Page Number: 1~ I1 of 23 ATTACHMENT A Page 4 of 4 EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS A U 00 0 0 20 IOU-00 ~0r M En. 0 -0 0 0 0ý-0~0 ~0 0a 0 0 0 0 0 E 0. 0 .4 00 0 >0-Z U.s. .0~~ 00. 0 cl- C', EE 0 0V 4< U U- 0 21 46 :ý -2 .I .~. -o 0 -a o k Beaver Valley Power Station ProcedureNumberC2.03 Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use: 1i:/2 General Skill Reference Revision: Page Number: 1 19 nf TI ATTACHMENT B Page 1 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-1 AIR SAMPLING LOCATIONS so j Procedure Number: Beaver Valley Power Station 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 13 of 23 ATTACHMENT B Page 2 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-1 (Continued) AIR SAMPLING LOCATIONS Sector Site # Distance (miles) Location S1! 13 1.49 Old Meyer Farm 4 30 J 0.43 Shippingport (Cook's Ferry S.S.)-15 32 j 0.75 Midland (North S.S.)2/3 46.1 j 2.28 Industry -McKeel's Service -Rt. 68 10 48 16.40 Weirton Water Tower, Collier Way Beaver Valley Power Station [Proedure Nu/2_ODC_2. 0 3 J Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use: 1/2 General Skill Reference. Revision: Page Number: 1 1 1.4 nf')ATTACHMENT B Page 3 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-2 TLD LOCATIONS 1 .1 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 1 15 of 23 ATTACHMENT B Page 4 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-2 (continued) TLD LOCATIONS. Southeast Sector Site # Distance Location Sector Site # Distance Location (miles) (miles)7 27 -.14 Brunton Farm 7 78 2.72 Raccoon Municipal Bldg.6 45.1 1.92 Raccoon Twp., Kennedy Comers 8 79 4.46 106 Rt. 151- Ted McWilliams Auto........... _ _ Body 5 51 8.00 Aliquippa (Sheffield S.S.) , 9 80 8.27 Raccoon Park Office, Rt. 18 6 59 0.99 236 Green Hill Road 9 82 6.99 2697 Rt. 18 6 76 3.80 Raccoon Elementary School 8 94 2.25 McCleary & Pole Cat Hollow Roads 6 77 5.52 3614 Green Garden Road Northwest Sector Site # Distance Location Sector Site # Distance Location (miles) (miles)14 15 3.75 Georgetown Post Office [ 14 87 7.04 50103 Calcutta Smith's Ferry Rd.15 32 0.75 Midland.North S.S.) 15 88 2.74 110 Summit Rd., Midland Heights 14 47 4.88 E, Liverpool Water Dept. 15 89 4.72 488 Smith Ferry Rd., Ohioville 13 60 2.51 444 Hill Road 16 90 5.20 6286 Tuscarawras Rd.13. 86 6.18 1090 Ohio Avenue, E. Liverpool .16 93 1.10 104 Linden- Sunrise Hills Northeast Sector Site # Distance Location Sector Site # Distance Location'(miles) mlsI 3/4 10 0.94 Shippingport Post Office 1 70 3.36 236 Engle Rd.1 28 8.60 Sherman Farm 2 71 6.01 Brighton Twp., First Western Bank 3 29B 7.97 Friendship Ridge 3 72 3.25 Ohioview Luthern Church -Rear 4 30 ..431 Shippingport (Cook's Ferry S.S.) 4 73 2.48 618 Squirrel Run Rd.5. 45 ýt2".19 Christian House Baptist 4 74 6.92 137 Poplar Ave. -CCBC Chapel -Rtl8 3 46 2.49 Industry, Midway Dr. 5 75 4.08 117 Holt Rd.2/3 46.1 2.28 Industry -McKeel's Service -2 91 3.89 Pine Grove Rd. & Doyle Rd.Rt68 __ _Southwest Sector Site # Distance Location Sector Site 1* Distance Location (miles) (miles) [11 13 1.49 Old Meyer Farm 11 84 8.35 Hancock Co. Senior Center 11 14 2.53 Hookstown Boro 12 85 5.73 2048 Rt. 30 10 48 16.40 Weirton Water Tower, Collier 12 92 2.81 Georgetown Rd. (Georgetown S.S.)Way 9 81 3.69 Millcreek United Presby. Church 10 95 2.37 832 McCle Rd.10 83 4.26 735 Mill Creek Rd. Beaver Valley Power Station Procedure Number:/2ODC2.03 Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use: I 1/2 General Skill Reference JA Revision: Page Number: I9 I 1 16 of 21 ATTACHMENT B Page 5 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-3 SHORELINE SEDIMENT, SURFACE WATER, AND DRINKING WATER SAMPLING LOCATIONS I Beaver Valley Power Station Procedure Number:* 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 17 of 23 ATTACHMENT B Page 6 of 12 LOCATION OF SAMPLING -SITES FIGURE 3.0-3 (Continued) SHORELINE SEDIMENT, SURFACE WATER, AND DRINKING WATER SAMPLING LOCATIONS SampieT7ype Sector Site # Distance (miles) Location Surface Water 14 2.1 1.43, Midland -ATI Allegheny Ludlam Surface Water 3 49 4.92 Upstream of Montgomery Dam Sediment 12 2A 0.31 BVPS Outfall Vicinity Sediment* 3 49a 4.93 Upstream of Montgomery Dam Drinking Water 15 4 1.26 Midland Water Dept.Drinking Water 14 5 4.90 East Liverpool Water Dept.Site #49a added -control site. Beaver Valley Power Station I Nujn,7:ODC-2.03 Title: ODCM: Radiological Environmental Monitoring Program Unit: Level Of Use:General Skill Reference .Revision: Page Number: 1 I lRof291 ATTACHMENT B Page 7 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-4 MILK SAMPLING LOCATIONS S I As Procedure Number: I: Beaver Valley Power Station 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 19of 23 ATTACHMENT B Page 8 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-4 (Continued) MILK SAMPLING LOCATIONS Sector Site # Distance (miles) Location 10 25 2.10 Searight Farm 10 96 10.48 Windsheimer Farm*Three dairies based on highest deposition factors. Procedure Number: Beaver Valley Power Station 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference,... Revision: Page Number: .1 20 of 23 S ATTACHMENT B Page 9 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-5 FOODCROP SAMPLING LOCATIONS Beaver Valley Power Station ProcdureNub 2 ODC 2 3 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision: Page Number: 1 21 of 23 ATTACHMENT B Page 10 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-5 (Continued) FOODCROP SAMPLING LOCATIONS Site # Description 10a Shippingport Boro 15a Georgetown Boro 46a Industry Boro 48a Weirton Area Beaver.Valley.Powe Station .Procedure Number:. .B~eaver Valley Power Station i 1/2-ODC-2.03.... TitMe: ODCM: Radiological Environmental Monitoring Program Unit: Revision: 1 Level Of Use: General Skill Reference J.Page Number:)7 nf ')ATTACHMENT B Page II of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-6 FISH SAMPLING LOCATIONS.1 Beaver Valley Power Station 2ProcedureNumber: 1/2-ODC-2.03 Title: Unit: Level Of Use: ODCM: Radiological Environmental Monitoring Program 1/2 I General Skill Reference Revision: Page Number: 1 1 I 23 of 23 ATTACHMENT B Page 12 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-6 (Continued) FISH SAMPLING LOCATIONS Sector Site # Distance (miles) Location 12 2A 0.31 BVPS Outfall Vicinity 3 49a 4.93 Upstream of Montgomery Dam PP77 RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.04 ODCM: Information Related to 40 CFR 190 Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 1 Level Of Use General Skill Reference Safety Related Procedure Yes Procedure Number: Beaver Valley Power Station 1/2-ODC-2.04 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number: 1 ~2 of 6--TABLE OF CONTENTS 1.0 PU RPO SE ........................................................................................................................................ 3 2.0 SCOPE ............................................................................................................................................ 3 3.0 REFEREN CES AN D COM M ITM ENTS ................................................................................... 3 3.1 References .............................................................................................................................. 3 3.2 Com m itm ents ........................ ................................................................................................ 3 4.0 RECORD S AN D FORM S .......................................................................................................... 3 4.1 Records .................................................................................................................................. 3 4.2 Form s ...................................................................................................................................... 4 5.0 PRECA OTION S AND LIM ITATION S ....................................................................................... 4 6.0 A CCEPTAN CE CRITERIA .......................................................................................................... 4 7.0 PREREQUISITES ........................................................................................................................... 4 8.0 PROCEDURE .................................................................................................................................. 5 8.1 Information Related To 40 CFR 190 .......................................... 5 8.2 Inside The Site Boundary Radiation Doses .................................................................... 6 Procedure Number: Beaver Valley Power Station 1/2-ODC-2.04 Title: Unit: Level Of Use:.1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number:, l3 of 6 1.0 PURPOSE 1.1 This procedure provides the steps to be taken when the Total Dose of ODCM Control 4.11.4.1 exceeds twice the limit of any of the ODCM Controls specifying an Offsite Dose Limit.(3.1.2)
1.1.1 Prior
to issuance of this procedure, these items were located in Section 4 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 40 CFR Part 190 3.1.2 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.4 1/2-ADM-0100, Procedure Writer's Guide 3.1.5 1/2-ADM-0101, Review and Approval of Documents 3.1.6 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.CA-18, Revise procedure 1/2-ODC-2.04 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.
3.2 Commitments
3.2.1 10 CFR 20.405(c), Special Reports 3.2.2 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)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. Beaver Valley Power Station Proce.dre Nomber:____ ___ ___ ___ ___ ____ ___ ___ ___ ___1/2-ODC-2.04 Title: Unit: Level Of Use: 1/2 General Skill Reference, ODCM: Information Related to 40 CFR 190 Revision: Page Number: L 4of6 ..0 4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The Offsite Dose Limits used to show compliance to this procedure are as follows: 5.1.1 ODCM Control 3.11.2.a; Liquid Effluents: < 1.5'mrem/quarter Total Body or< 5 mrem/quarter any Organ.5.1.2 ODCM Control 3.11.2.b; Liquid Effluents: < 3. mremryear Total Body or<10 mrem/year any Organ.5.1.3 ODCM Control 3.11.2.2.a; Gas Effluent-Noble Gas: < 5 mrad/quarter Gamma, or< 10 mrad/quarter Beta 5.1.4 ODCM Control 3.11.2.2.b; Gas Effluents-Noble Gas: < 10 mrad/year Gamma< 20 mrad/year Beta 5.1.5 ODCM Control 3.11.2.3.a; Gas Effluents-Particulates & Iodines: < 7.5 mrem/quarter any organ 5.1.6 ODCM Control 3.11.2.3.b; Gas Effluents-Particulates & Iodines: < 15 mrem/year any organ 5.1.7 ODCM Control 3.11.4.1; All Fuel Cycle Sources: < 25 mrem/year Total Body or any Organ, except the thyroid, which is limited to < 75 mrem/year 6.0 ACCEPTANCE CRITERIA 6.1 Any 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 setpoint calculation.(' 2 2)6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-01 00(3.1.4)and 1/2-ADM-t 640.(3'3)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0 101 3.1.5) and 1/2-ADM- 1640.(313)
7.0 PREREQUISITES
7.1 The user of this procedure shall be familiar with ODCM structure and content. Beaver Valley Power Station ProceureN ODC 2 0 4 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number: 1 .5 of 6 8.0 PROCEDURE 8.1 Information Related To 40 CFR 190 8.1.1 CONTROL 3.11.4.1 requires that when the calculated doses associated with the effluent releases exceed twice the limits of ODCM CONTROL 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, the following shall be performed: 8.1.1.1 Calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the dose or dose commitment to any MEMBER OF THE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources exceeds the limits of< 25 mrem to the total body or any organ, except the thyroid, which is limited to< 75 mrem for a calendar year.8.1.1.1.1 8.1.1.1.1.1 8.1.1.1.1.3 8.1.1.1.1.4 8.1 .1.1.1.5 If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to 10 CFR 20.405(c).(3 2.) The following shall be included in the Special Report: Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM CONTROL 3.11.4.1.Include the schedule for achieving conformance within the limits of ODCM CONTROL 3.11.4.1.Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.Describe levels of radiation and concentrations of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the limits of ODCM CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a variance in accordance with the provisions of 40 CFR Part 190.Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. Beaver Valley Power Station I PoedureN1 r:/2.ODC2.0 4 Title: Unit: Level Of Use: 1/2 IGeneral Skill Reference Revision: Page Number: I II ODCM: Information Related to 40 CFR 190 8.2 Inside The Site Boundary Radiation. Doses 8.2.1 In regards to assessment of radiation doses (from Radioactive Effluents) to MEMBERS OF THE PUBLIC due to their activities inside the site boundary, the following is provided: 8.2.1.1 A separate assessment of radiation doses from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the site boundary is generally not necessary because the exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary.8.2.1.2 For reporting purposes, separate guidance for calculating radiation doses to a MEMBER OF THE PUBLIC inside the site boundary is not needed because the dose assessments for an offsite MEMBER OF THE PUBLIC is also assumed to be for a MEMBER OF THE PUBLIC conducting activities onsite.8.2.1.2.1 This is verified by showing that the ground release X/Q dispersion parameter used for dose calculation at the site boundary (0.352 miles NW) is greater than the X/Q dispersion parameter at the location where a MEMBER OF THE PUBLIC would most likely have the maximum exposure time (0-0.5 miles N and 0-0.5 miles NNW). A comparison of these x/Q dispersion parameters is as follows: X/Q Used for Dos X/Q Wh anAssumed Q R&ieces Calculation MEMBEROF THE PUBLIC fiom Would Most Likely Have the Maximum 1/2-ODC-2.02 E~xposui Time SiteBodary Inside the Site Inside the Sit SeeAtfa1cim F 0352 miles NW Boundary Bounidary 0-0.5 miles N 0-0.5 miles NNW 924E-5 secm 3 233E-5 secr 3 5.47E-5 secin 3 Table 2.2-4 1.03E4 se)m 3 2.76E-5 sec=4 6.01E-5 sec&r? Table 2.2-5 7.35E-5 secm 3 2.44E-5 5.57E-5 sec/i 3 Table 22-7 924E-5 se/mr? 2.33E-5 secin 3 5.47E-5 secn 3 Table 22-8 924E-5 =In?3 233E-5 3 5.47E-5 sec/i 3 Table 22-9 7.35E-5 secW 3 2.44E-5 soch 3 5.57E-5 sed/in 3 Table 22-10-END - RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.01 ODCM: Dispersion Calculation Procedure and Source Term Inputs Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 1 Level Of Use General Skill Reference Safety Related Procedure Yes-r I.TABLE OF CONTENTS 1.0 PU R P O S E ......................................................................................................................................... 3 2 .0 : S C O P E .................................................... .......................................................................................... 3 3.0 REFEFERENCES AND COMMITMENTS ..................................... 3 3.1 R eferences .............................................................................................................................. 3 3.2 C om m itm ents ......................................................................................................................... 4 4.0 RECORD S AND FORM S ....................................................................................................... 4 4 .1 R eco rd s ................................................................................................................................... 4 4.2 Forms ............................................................ 4 5.0 PRECACTIONS AND LIMITATIONS ...................................................................................... 4 6.0 A CCEPTAN CE CRITERIA ........................................................................................................ 4 7.0 PR E R E Q U ISIT E S ............................................................................................................................ 4 8.0 PROCEDURE .............................................. ........... 5 8.1 Summary of Dispersion and DepositionMethodology ...................................................... 5 8.2 Summary of Source Term Inputs ........................................ 7 8.2.1 Liquid Source Term Inputs ............................................................................... 7 8.2.2 Gaseous Source Term Inputs ........................................... ................................. 7 ATTACHMENT A ............................................................ BV-I AND 2 RELEASE CONDITIONS ATTACHMENT B ....................... ....... LIQUID SOURCE TERM INPUTS.-: ATTACHMENT C ........................... GASEOUS SOURCE TERM % Beaver Valley Power Station Proeedure Number: Beaver V1/2-ODC-3.01 Tie: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: 1 -_3 of 12 1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calculating dispersion (X/Q)and deposition (D/Q).1.1.1 Prior to issuance of this procedure, these items were located in Appendix A of the old ODCM.1.2 This procedure also contains the input parameters to the various computer codes used by the Licensee and its subcontractors for determination of the liquid and gaseous source term mixes,.1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old ODCM.2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
3.0 REFEFERENCES
AND COMMITMENTS
3.1 References
3.1.1 NUS-2173, Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station, For the Straight-Line Atmospheric Dispersion Model, NUS Corporation, June 1978 3.1.2 NUREG/CR-2919, XOQDOQ: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, September, 1982 3.1.3 Regulatory Guide 1.23, Meteorological Measurement Program for Nuclear Power Plants 3.1.4 Regulatory Guide 1. 111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Coded Reactors, Revision 1, July 1977 3.1.5 NRC Gale Code, 3.1.6 SWEC LIQIBB Code, 3.1.7 SWEC GASIBB Code, 3.1.8 NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)3.1.9 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual Beaver Valley Power Station 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference-,¶ ODCM: Dispersion Calculation Procedure and Source Term: Inputs Revision:, Page Number: 1-. 1 4 of 12 3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval of Documents 3.1.12 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.CA-19, Revise procedure 1/2-ODC-3.01 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.
3.2 Commitments
3.2.1 None 4.0 RECORDS ANDFORMS 4.1 Records 4.1.1 Any calculation supporting generation of dispersion, deposition, or source term mixes 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 This procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-1 and 2 Offsite Dose Calculation Manual.5.1.1 In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate ATTACHMENTS of this procedure will still contain a prefix denoting an "A" or "B".6.0 ACCEPTANCE CRITERIA 6.1 Any change 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 CER 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 setpoint calculation. 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3.'° 0)and 1/2-ADM-1640.(3'1.9)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-0101(3-'ll) and 1/2-ADM-1640.(3'9)7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content. Beaver Valley Power Station Procedure Number:~1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: 1 1 5 of 12 8.0 PROCEDURE 8.1 Summary of Dispersion and Deposition Methodology
8.1.1 Annual
average and grazing season average values of relative concentration (x/Q) and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflow (Gaussian) model described in RG 1.1 l.(3.1.4)8.1.1.1 Undecayed and undepleted sector average XIQ and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors. 8.1.1.2 For an elevated release, (i.e.; occurring at a height that is twice the height or more of a nearby structure) credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.8.1.1.3 A building wake correction factor was used to adjust calculations for ground-level releases.8.1.1.4 Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site.P8.1.1.5 The methodology employed in the calculation of intermittent release x/Q and D/Q values is that described in NUREG/CR-2919.(312) 8.1.2 The site continuous gaseous release points that have been evaluated include the following: 8.1.2.1 PV-1/2: The Unit 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower 8.1.2.2 CV-1 and CV-2: The Unit 1 Rx Containment/SLCRS Vented the Unit 2 SLCRS Filtered Pathway 8.1.2.3 VV-1 and VV-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway 8.1.2.4 TV-2: The Unit 2 Turbine Building Vent 8.1.2.5 CB-2: The Unit 2 Condensate Polishing Building Vent 8.1.2.6 DV-2: The Unit 2 Decontamination Building Vent 8.1.2.7 WV-2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3 The intermittent releases are from PV-1/2, VV-1, VV-2, CV-1 and CV-2. Procedure Number:*Beaver Valley Power Station 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference .ODCM: Dispersion Calculation Procedure and Source Term Inputs 1Revision: Pg 1 I 6 of 12 8.1.4 Only PV-1/2 was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is given in ATTACHMENT A.8.1.5 Onsite meteorological data for the period January 1, 1976 through December 31, 1980 were used as input for the annual-average calculations. 8.1.5.1 The grazing season was represented by a six-month period from May I through October 31 for each year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season.8.1.5.2 The data were collected according to guidance in NRC RG-1.23(3'1.3) as described in Section 2.3 of the BVPS-2 FSAR.8.1.5.3 The parameters used in the X/Q and D/Q calculations consist of wind speed, wind direction, and AT as an indicator of atmospheric stability. The lower level winds (35 ft) and AT (150-35 ft) were used for all release points except the Process Vent which required the use of 500 ft winds and AT (500-35 ft) which are representative of the release height (510 ft).8.1.6 The annual average and grazing season X/Q and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal.8.1.6.1 In the case of the Process Vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum X/Q and D/Q values.8.1.6.2 The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of 1/2-ODC-2.02. 8.1.6.3 The continuous release annual average X/Q values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent, and Condensate Polishing Building Vent are given in ATTACHMENT F (Tables 2.2-4 through 2.2-10) of 1/2-ODC-2.02. Continuous release annual average X/Q's for these same release points are also given at ten incremental downwind distances of 0-5 miles.8.1.6.4 Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of 1/2-ODC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.3-28 through 2.3-34) of 1/2-ODC-2.02 for the special locations. 8.1.6.5 Due to their location adjacent to the Containment Building, the Decontamination -*Building and Gaseous Waste Storage Tank Vault X/Q's and D/Q's are the same as the Containment Vent X/Q's and D/Q's. Beaver Valley Power Station ProcedureNmber: ODC-3.1 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: 1 7 of 12 8.1.6.6 Likewise, the Turbine Building Vent X/Q's and D/Q's apply to the Condensate Polishing Building as well due to its location adjacent to the Turbine Building.8.1.7 ATTACHMENT M (Tables 2.3-35 through 2.3-38) of 1/2-ODC-2.02 contain short term X/Q values for batch releases originating from the Containment Vent, Ventilation Vent, and Process Vent releases respectively. 8.1.7.1 The values in these tables are based on 32 hours per year of Containment and Ventilation Vent purges and 74 hours per year of Process Vent purges.8.2 Sumnmry of Source Term Inputs 8.2.1 Liquid Source Term Inputs 8.2.1.1 Inputs to the NRC Gale Code used for generation of BV- I Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: I a).8.2.1.2 Inputs to the SWEC LIQ1BB Code used for generation of BV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: lb)8.2.2 Gaseous Source Term Inputs 8.2.2.1 Inputs to the SWEC GAS 1BB Code for generation of BV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a)8.2.2.2 Inputs to the SWEC GAS 1BB Code for generation of BV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2b) Beaver Valley Power Station Procedure Numr: Title: Unit: Level Of Use: 1/2 General Skill Reference.,. I Revision: Page Number: .ODCM: Dispersion Calculation Procedure and Source Term Inputs 1,. I otf I ATTACHMENT A Page 1 of 1 BV- I AND 2 RELEASE CONDITIONS TABLE A:-VV-I VENTILATION VENT (PAB EXHAUST)VV-2 SLCRS UNFILTERED PATHWAY CV-I RX CONTAINMENT/ SLCRS VENT CV-2 RX CONTAINMENT/ SLCRS FILTERED PATHWAY PV-I/2 GASEOUS WASTE/PROCESS VENT TV-2 TURBINE BUILDING VENT TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL Long Term And LongTam And Long Term And LongTenn And ShodTerm Shod Tmn ShortTem ShoiTen m Releas Point Height (m)Adjaent Building Height(m)Relative LocafionTo Adjacentm Stu Exit Velocity(m/sec) kntema StkBuilding Cross-Sectional Aea (m 2)Purge Purge Duration fthileae)26 19 47 44 155 155 33 33 E. Side Offtrimy Awdlimy Bldg Top Ceater Of Cormiaet Dome Atop CoolingTower Tuibine Building NA NA 1600 32 8 NA NA 1600 32 8 9.4 0.25 NA NA NA NA NA NA 74 NA*Applied to Short Term calculations only Beaver Valley Power Station Proced ureN- :ODC-3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: 19 9of 12 ATTACHMENT B Page 1 of 2 LIQUID SOURCE TERM INPUTS TABLE B:la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-I PWR INPUTS VALUE Thermal Power Level (megawatts) Plant CapacitS7 Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)Mass Of Steam In Each Steam Generator (thousand lbs)Mass'Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction RadwasteDilution Flow (thousand gpm)2766.000.800 345.000.120 60.000 6.000 3.000 11.620 6.772 97.000 1296.000 291.000 33.900 100.000.001.010 0.000 22.500 BV-I LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day) OF PCA DISCHARGE (days) (days) I Cs OTHERS Shim Bleed Rate Equipment Drains 1.32E4 6.00E2 1.000 1.000 1.000 0.035 Clean Waste 7.50E1 Input 0.000 0.000 1.000 1.000 1.000 11.260 7.220 1E7 IE7 1E7 11.260 7.220 1E7 IE7 1E7 Dirty Waste Input 1.35E3 0.071 0.071 0.071 0.648 1E5 2E4 1E5 0.648 IE5 2E4 1E5 0.648 1E5 2E4 IE5 Blowdown 9.75E4 Untreated Blowdown 0.0 Beaver Valley Power Station ProcedureNumbeo: ... ** .. 12,ODC-3.o1 Title: .Unit: Level Of Use 1/2 General Skill Reference -I ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: 1 : 10 of 12 ATTACHMENT B Page 2 of 2 LIQUID SOURCE TERM INPUTS TABLE B:lb INPUTS TO SWEC LIQ1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percen& Fuel With Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 Mass Of Water In Steam Generator (thousand ibs) 298.000 Blowdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 Radwaste Dilution Flow (thousand gpm) 7.800 BV-2 LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day) OF PCA DISCHARGE (his) (hrs) I CsRb OTHERS Containment 40 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Sump Auxiliary 200 0.100 1.0 35.5 6.2 IE3 1E4 IE4 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 IE3 IE4 IE4 Sources Rx Plant 35 1.000 1.0 *35.5 6.2 IE3 IE4 IE4 Samples Lab Drains 400 0.002 1.0 35.5 6.2 1E3 iE4 1E4 Cond. Demin. 2685 1.IE-4 1.0 35.5 6.2 IE3 1E4 IE4 Rinse Water , CVCS 60 -- 1.0 1300 173 1E4 4E3 1E5 Turbine 7200 -- 1.0 Bldg.Drains Beaver Valley Power Station PeUre Nit be: Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number: " 1 " 11 of 12 ATTACHMENT C Page 1 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2a INPUTS TO SWEC GAS IBB CODE FOR GENERATION OF BV-I GASEOUS SOURCE TERM MIXES BV-1 PWR INPUTS Thermal Power Level (megawatts) Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr),Mass Of Steam In Each Steam Generator (thousand lbs)Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand Ibs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)VALUE 2766.000.800 385.000.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298,000 52.000 100.000.001.010 0.000 15.000 BV-1.GASEOUS WASTE INPUTS There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)Hold Up Time For Krypton (days)Primary Coolant Leak To Auxiliary Building (lb/day)Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (million cu-ft)Frequency Of Primary Coolant Degassing (times/yr) Primary To Secondary Leak Rate (lb/day)There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfmt)Purge Time Of Containment (hours)There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq) In Steam Generator' Frequency Of Containment Building High Vol Purge (times/yr)* Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/hr)Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System VALUE 39.000 2.000 160.000 7.5E-3 0.000 1.000 1.000 1.800 2.000 100.000 2.000 8.000 0.010 4.000 1.000 1.000 1700.000 0.000 0.440*2 cold and 2 hot purges r Procedure Number: I Title: ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT C Page 2 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2b INPUTS TO SWEC GAS IBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS Thermal Power Level (megawatts) Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)Mass Of Steam In Each Steam Generator (thousand lbs)Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand Ibs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)VALUE 2766.000.800 385.000.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000.001.010.700 7.800 VALUE 45.800 2.570 160.000 7.5E-3 0.000 0.100 0.010 1.800 21000 100.000 20.000 8.000 BV-2 GASEOUS WASTE INPUTS There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)Hold Up Time For Krypton (days)Primary Coolant Leak To Auxiliary Building (lb/day)Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (million cu-ft)Frequency Of Primary Coolant Degassing (times/yr) Primary To Secondary Leak Rate (lb/day)There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfmn)Purge Time Of Containment (hours)There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)* Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/hr)Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Ts Not A Off Gas System 0.010 4.000 1.000 1.000 1700.000 0.000 0.270 Th r s o .... .... .... O ffL' G.. ...r ......*2 cold and 2 hot purges RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.02 ODCM: Bases For ODCM Controls Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 2 Level Of Use General Skill Reference Safety Related Procedure Yes Beaver Valley Power StationProcedure Number: i/2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls General Skill Reference Revision: Page Number: TABLE OF CONTENTS 1.0 P U R PO SE ........................................ ................................................................................................. 3 2.0 SOPE........... ................................................. 2.0 SCOP N E A D CO MTEN T ............... ........................ .. .... ...*.... i..... .......*.. ..... ................. 3
3.0 REFERENCES
AND COMMITMENTS .................... ......................... 3 3.1 References........................................................................................... 3 3.2 C om m itm ents .......................................................................................................................... 4 4.0 RE CO RD S AN D FORM S ............................................................................................................... 4 4.1 R ecords ......... ........ ........................................................................ ............................... 4 4 .2 F orm ss ..................................................................................................................................... 5 5.0 PRECAU.TIONS AND LIMITATIONS ........................................................................................... 5 6.0 ACCEPTANCE CRITERIAT.ATIONS............................................................................................ 5 7.0 PR E R E Q U ISIT E S ............................................................................................................................ 5 8.0 PR O C E D U RE .................................................................................................................................. 5 ATTACHMENT A BASES FOR ODCM CONTROLS: INSTRUMENTATION .......................... 7 ATTACHMENT B BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS .......................... 8 ATTACHMENT C BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS .................... 10 ATTACHMENT D BASES FOR ODCM CONTROLS: TOTAL DOSE ...................................... 13 ATTACHMENT E BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL M ONITORING PROGRAM (REM P) ........................................................................................... p 0 Beaver Valley Power Station Procedure Number: 1/2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: 2 3 of 14 1.0 PURPOSE 1.1 This procedure contains the Bases for the ODCM Controls that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments lA-I 88/2A-70, and in accordance with Generic Letter 89-01 and NUREG- 1301 (Generic Letter 89-01, Supplement No. 1) [ITS] and T.S. 5.5.2. 3210)1.1.1 Prior to issuance of this procedure, these items were located in Appendix D of the old ODCM.1.2 This procedure also contains the Bases for the ODCM Controls (for Radiation Monitoring Instrumentation) that were duplicated from, the Bases Section of the Technical Specification per Unit 1/2 Amendments I A-246/2A-124, and in accordance with NUREG- 1431 .(3 1.6,3.2.11). 1.3 This procedure also contains the Bases for the ODCM Controls (for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits) that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments 1A-250/2A-130, and in accordance with NUREG- 1431 .(3.1.7, 3.2.11)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 1/2-ODC-2.01, ODCM: Liquid Effluents 3.1.2 1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.4 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.5 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-188/2A-70 (LAR I A- 175/2A-37), Implemented August 7, 1995 3.1.6 Unit 1/2 Technical Specification 3.3.3.1, including Amendments I A-246/2A-124 (LAR IA-287/2A-159), Implemented April 11, 2002 3.1.7 Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5 and 6.8.6, including Amendments IA-250/2A-130 (LAR IA-291/2A-163), Implemented August 7, 2002 3.1.8- 1/2-ADM-0100, Procedure Writer's Guide 3.1.9 1/2-ADM-0101, Review and Approval of Documents Beaver Valley Power Station ProcedureNumber: ý1/2:ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: 2 4 of14 ..3.1.10 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.CA-20, Revise procedure 1/2-ODC-3.02 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental and Chemistry. CR 05-03306, Incorporated Improved Technical Specifications (ITS).3.1.11 [ITS] T.S. 5.5.2 3.2 Commitments 3.2.1 10 CFR Part 20 3.2.2 10 CFR Part 50 3.2.3 40 CFR Part 141 3.2.4 40 CFR Part 190 3.2.5 Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I, Revision 1, October, 1977 3.2.6 Regulatory Guide 1.111, Methods For. Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, July, 1977 3.2.7 Regulatory Guide 1.113, Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix I, April, 1977 3.2.8 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978.3.2.9 NUREG-0737, Clarification of TMI Action Plan Requirements, October, 1980 3.2.10 NUREG-1301, Offsite Dose Calculation Manual Guidance. Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)3.2.11 NUREG-1431, Standard Technical Specifications -Westinghouse Plants Specifications
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 (eg; letter or calculation package) with an appropriate RTL number. Procedure Number: Beaver Valley Power Station 1/2-ODC-3.02 Title: Unit Level Of Use: ODCM:. Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: 2 5 of 14 4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The numbering of each specific ODCM Bases contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Bases numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbezing changes.5.2 This procedure includes Improved Technical Specifications ([ITS]) information that is NOT applicable to current Technical Specifications ([CTS]) and [CTS] information that is NOT applicable in [ITS]. The [CTS] information shall be used prior to the [ITS] effective date.The [ITS] information shall be used on or after the [ITS] effective date.6.0 ACCEPTANCE CRITERIA 6.1 Any change 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 Appenidx I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.(3. 2 10)6.1.1 All changes to this. procedure shall be prepared in accordance with 1/2-ADM-0 1 00(3 18)and 1/2-ADM-1640.(3 14)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0 101(3.1.9) and 1/2-ADM- 1640.(3.1.4)
7.0 PREREQUISITES
7.1 The user of this procedure shall be familiar with ODCM structure and content.8.0 PROCEDURE 8.1 See ATTACHMENT A for a complete description of Bases for ODCM Controls associated with Instrumentation. 8.2 See ATTACHMENT B for a complete description of Bases for ODCM Controls associated with Liquid Effluents. 8.3 See ATTACHMENT C for a complete description of Bases for ODCM Controls associated with Gaseous Effluents. 8.4 See ATTACHMENT D for a complete description of Bases for ODCM Controls associated with Total Dose. Procedure Number.Beaver Valley Power Station l/2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference_ Revision: Page Number: 8.5 See ATTACHMENT E for a complete description of Bases for ODCM Controls associated with the Radiological Environmental Monitoring Program (REMP).-END-Beaver Valley Power Station Procedure Number: 1/2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: 27 7of14 ATTACHMENT A Page 1 of I BASES FOR ODCM CONTROLS: INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORINGINSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that: 1) the radiation levels are continually measured in the areas served by the individual channels;
- 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded;-and 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of NUREG-0737.' 2'9)3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with Section 1 of this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.(3"2.1, 3.2.2)3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with Section 2 of this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.(32I. 3.2.2) 5 I Title: ODCM: Bases For ODCM Controls ATTACHMENT B Page 1 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 3/4.1.1.1.1 LIQUID EFFLUENT CONCENTRATION This CONTROL is provided to ensure that the concentration of radioactive materials released in Liquid waste effluents from the site to unrestricted areas will be less than 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20-2402), Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section II.A design objectives of Appendix 1, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.(32I1 3.2.2)3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the procedure 1/2-ODC-2.01 implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in procedure 1/2-ODC-2.01 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1. 109, and Regulatory Guide 1.113. NUREG-0 133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.1.I,3.22,3.2.3,3.2.5,3.2.7, 3.2.8)This CONTROL applies to the release of liquid effluents for Beaver Valley Power Station, Unit No. I or Unit No. 2. These units have shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. Beaver Valley Power Station ProcedureN1um17 ...ODC 3..2 Title: Unit: Level Of Use: " ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: " 2 9 of 14 ATTACHMENT B Page 2 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be*kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section I.D of Appendix I to 10 CFR Part.50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid, effluents. This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2.(322)3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides-assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. Procedure Number:'Beaver Valley Power Station 1/2-ODC-3.02 I Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls Revs1/2io General. Skill Reference[Revision: Page Number: S 2 10 of 14 .ATTACHMENT C Page I of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.1 GASEOUS EFFLUENT DOSE RATE This CONTROL is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to < 500 mrem/year to the total body or to<3,000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background of a child via the inhalation pathway to < 1,500 mrem/year.(3, 2'1)3/4.11.2.2 DOSE, NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that'the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in procedure 1/2-ODC-2.02 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide I. 109, and Regulatory Guide I. Ill. The equations in procedure 1/2-ODC-2.02 are provided for determining the air doses at the exclusion area boundary, and are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. I or Unit No. 2.(312, 3.2.2, 3.2.5, 3.2.6, 3.2.8) Beaver Valley Power Station Procedure Number: B1/2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: 2 11 of 14.I ATTACHMENT C Page 2 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I.(3.2.2)-The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The calculational methods in procedure 1/2-ODC-2.02 are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: I) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. This CONTROL applies to radioactive material in particulate form and radionuclides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2.'"2' 3.2.2, 3.2.6, 3.2.7) Procedure Number: Beaver Valley Power Station*i/2- ODC-3.02 Title: Unit: Level Of Use: 1 ODCM: Bases For ODCM Controls 1/2, General Skill Reference Revision: Page Number: 4 2 12 of 14 ATTACHMENT C Page 3 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents. This specification applies to gaseous radwaste from Beaver Valley Power Station, Unit No. I or Unit No. 2.("1.2' 3.2.2)3/4.11.2.5 BV-1 GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting: total body exposure to an individual Slocated at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in each gas storage tank was specified to ensure that the total body exposure resulting fromrthe postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11 (a)(1).3/4.11.2.5 BV-2 GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.1 l(a)(1). The curie content limit is applied individually to each gaseous waste storage tank and collectively to the number of unisolated gaseous waste storage tanks. Beaver Valley Power Station PrcedureNu r:DC 3 0 2 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision: Page Number: "2 13 of 14...ATTACHMENT D Page 1 of 1 BASES FOR ODCM CONTROLS: TOTAL DOSE 3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses due to-releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 nmrems to the whole body or any organ, except the thyroid, which shall be limited to less than, or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikley that the resultantdose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is :negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM CONTROL 3.11.11.1 and 3.11.2. 1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.(3"I-3' 3.2.1, 3.2.2, 3.2.4) Procedure Number: Beaver Valley Power Station 11o -oC-3.e.* /2-ODC-3.02 Title: Unit: Level Of Use: ODCM: Bases For ODCM Controls 1/2 , General Skill Reference-, Revision: Page Number: " 1 2 14 of14 " ATTACHMENT E Page 1 of 1 BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of MEMBER(S) OF THE PUBLIC resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may beinitiated based on operational experience. The detection capabilities required by ODCM Control 3.12.1, Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's J for drinking water meet the requirements of 40 CFR 141.(3.'1'3 3.2.3)3/4.12.2 LAND USE CENSUS ODCM CONTROL 3.12.2 is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring programs are made if required by the results of this census. The best survey information from the door-to-door survey, aerial survey, or by consulting with local agriculture authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.(3 1.3' 3.2.2)3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The ODCM CONTROL 3.12.3 for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.(3'1'3) RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.03 ODCM: Controls for RETS and REMP Programs Document Owner Manager, Nuclear Environmental and Chemistry ReVision Number 4 Level Of Use General Skill Reference Safety Related Procedure Yes Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: ODCM: Controls for RETS and REMP Programs Unit: Level Of Use: 1/2 General Skill Reference Revision: Page Number: 4 1 ?2 of 79 (4 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 TABLE OF CONTENTS PU RPO SE ............ ...... ......................................................................................................... I ........... 3 SCOPE .... ..................................................................................... 3 REFEREN C ES AN D CO M M ITM EN TS ........................ .................... ........ ........... 3 3.1 References .............................................................................................................................. 3 3.2 Com m itm ents ......................................................................................................................... 6 RECO RD S A N D FO RM S ......................................................................................................... 7 4.1 Records .................................................................................................................................. 7 4.2 Form s ...................................................................................................................................... 7 PRECA U TIO N S A N D LIM ITATIO N S....................................................................................... 7 A CCEPTAN CE CRITERIA ......................................................................................................... 7 PRE REQ U ISITES ............................................................................................................................ 7 PRO C ED U RE .................................................................................................................................. 8 ATTACHMENT A ATTACHMENT B ATTACHMENT C ATTACHMENT D ATTACHMENT E ATTACHMENT F ATTACHMENT G ATTACHMENT H ATTACHMENT I ATTACHMENT J ATTACHMENT K ATTACHMENT L ATTACHMENT M ATTACHMENT N ATTACHMENT 0 ATTACHMENT P ATTACHMENT Q ATTACHMENT R ATTACHMENT S ATTACHMENT T ATTACHMENT U ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY N O T A T IO N ........................................................................................................ 9 ODCM CONTROLS: DEFINITIONS ............................................................... 11 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQ U IREM EN TS ......................................................................................... 14 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION 17 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID -j EFFLUENTS ............................................. 25 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES... 35 ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION ............... 48 LIQUID EFFLUENT DOSE ...................................... 53 LIQUID RADWASTE TREATMENT SYSTEM ......... 54 LIQUID HOLDUP TANKS ...................................... 55 GASEOUS EFFLUENT DOSE RATE ...................... 56 DOSE- NOBLE GASES ............................................. 61 DOSE -RADIOIODINES AND PARTICULATES ...... 62 GASEOUS RADWASTE TREATMENT SYSTEM .... 63 GAS STORAGE TANKS ........................................... 64 TOTAL DOSE ............................................................ 65 REMP-PROGRAM REQUIREMENTS ........... 66 REMP -LAND USE CENSUS .................................. 74 REMP -INTERLABORATORY COMPARISON PR O G RA M ................................................ ..................................................... 75 ODCM CONTROLS: ANNUAL REMP REPORT..................................... 76 ODCM CONTROLS: ANNUAL RETS REPORTS ...................................... 78 a Beaver Valley Power Station Procedure Nunmbr: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number.4 .3 of 79 1.0 PURPOSE 1.1 This procedure includes selected Definitions and Tables as delineated in Section I of the Technical Specifications and selected Applicability and:Surveillance Requirement statements as delineated in Section 3/4 of the Technical Specifications.
1.1.1 Prior
to issuance of this procedure,, these items were located in Appendix C of the old ODCM, and were added to* this procedure for reference purposes, even though they are currently described in the Technical Specifications. 1.2 This procedure contains the controls for the Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specifications per Unit 1/2 Amendments 1 A- 188/2A-70, and in accordance with Generic Letter 89-01 and NUREG- 1301.('2-'0)1.2.1 Prior to issuance of this procedure, these items were located in Appendix C of the old ODCM." 1.3 This procedure contains the reporting requirements for the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report that were transferred from the Technical Specifications per Unit 1/2 Amendments 1 A-188/2A-70 and in accordance with Generic Letter 89-01 and NUREG-1301. (3210)1.3.1 Prior to issuance of this procedure, these items were located in Appendix E of the old ODCM.1.4 This procedure contains the controls for Radiation Monitoring Instrumentation that were transferred from the Technical Specification per Unit 1/2 Amendments 246/124, and in accordance with NUREG- 143 1. (3.2.11)1.5 This procedure contains the controls for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits that were transferred from the Technical Specification per Unit 1/2 Amendment 250/130, and in accordance with NUREG-1431 .1.6-,3.2.11 2)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 1/2-ODC-2.01, ODCM: Liquid Effluents 3.1.2 1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3 1/2-ODC-3.02, ODCM: Bases for ODCM Controls IPProcedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Referencedllk ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 4 of 79 3.1.4 Unit 1/2 Technical Specification 6.8.6, including Amendments 188/70 (LAR IA-175/2A- 137) Implemented August 7, 1995.3.1.5 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 246/142 (LAR 1A-287/2A- 159) Implemented April 11, 2002 3.1.6 Unit 1/2 Technical Specification 3.11.1.4, 3.11.2.5, 6.8.6 and 6.9.3, including Amendments 250/130 (LAR I A-291/2A-163) Implemented August 7, 2002 3.1.7 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.8 1/2-ADM-0100, Procedure Writer's Guide 3.1.9 NOP-SS-3001, Procedure Review and Approval 3.1.10 CR 981489, ODCM Table 4.11-2 Row A (Waste Gas Storage Tank Discharge). CA-01, Revise Appendix C of the ODCM (Table 4.11-2) to add clarification as to where and when tritium samples are to be obtained for GWST discharges. 3.1.11 CR 981490, ODCM Table 4.11-2 Note e, and Related Chemistry Department Procedures. CA-01, Revise Appendix C of the ODCM (Table 4.11-2, note e) to specify the proper tritium sample point.3.1.12 CR 993021, Apparent failure to test RM- 1 DA- 100 trip function as required by ODCM.No ODCM changes are required for this CR.3.1.13 CR 001682, ODCM Action 28 Guidance. CA-02, Revise Appendix C of the ODCM (Table 3.3-13, Action 28) to differentiate actions associated with Inoperable Process Flow Rate Monitors vs. Sample Flow Rate Monitors.3.1.14 CR02-0571 1, TS and ODCM changes not reflected in 1OM.54.3.L5 Surveillance Log.CA-01, Revise 1/2-ODC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes.3.1.15 CR03-06123, Enhance Table 3.3-6 of 1/2-ODC-3.03 to Add More Preplanned Method of Monitoring. CA-01, Revise Table 3.3-6 and Table 4.3-3 to allow use of Eberline SPING Channel 5 as an additional 2"d PMM when the Unit 1 Mid or High Range Noble Gas Effluent Monitors are Inoperable. 3.1.16 CR03-06281, Gaseous Tritium Sampling Required by ODCM (I/2-ODC-3.03) Unclear for Chemistry. CA-01, Revise procedure Attachment K Table 4.11-2 for RP:&Chemistry sampling of Gaseous Effluent Pathways to 'show which effluent pathways need sampled for compliance to ODCM Control 3.11.2.1 requirements. Beaver Valley Power Station Procedure Number C 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number 4 5 of 79 3.1.17 CR03-07487, Results of NQA Assessment of the Radiological Effluents Program. CA-01, Revise Calculation Package No. ERS-ATL-95-007 to clarify the term "Surface Water Supply" per guidance presented in NUREG-0800 SRP 15.7.3. CA-05, Revise 1/2-ODC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.3.1.18 CR03-07668, Benchmark Effluent & Environmental Programs VS Papers Presented at 13th REMP/RETS Workshop. CA-01, Evaluate procedure Attachment K Table 4.11-2 to reduce the amount of Effluent Samples obtained during a power transient. 3.1.19 CR03-09288, LAR IA-321 & 2A-193, Increased Flexibility in Mode Restraints. CA-19, Review LAR IA-321/2A-193.to identify the affected Rad Effluent procedures, programs, manuals, .and applicable plant modification documents that will need to be revised to support implementing the LAR.3.1.20 CR03-09959, RFA-Rad Protection Provide Clarification to ODCM I/Day Air Tritium Sample. CA-01, Revise ODCM procedure 1/2-ODC-3.03 Attachment K (Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere. 3.1.21 CR03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment 0, Control 3.11.2.5 to correct a typographical -error. Specifically, the final word in Action (a) needs changed from "nad" to "and".3.1.22 CR04-01643, Procedure Correction-Typographical Error in the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to correct a typographical error. Specifically, the Asset Number for the Vacuum Gauge used for measurement of sample flow (from the Alternate Sampling Device) needs changed from [PI-1GW-13] to [PI-IGW-135]. 3.1.23 CR04-02275, Discrepancies in Table 3.3-13-of the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to add clarification that the "Sampler Flow Rate Monitors are the devices used for "Particulate and Iodine Sampling". 3.1.24 Unit I Technical Specification Amendment No. 275 (LAR IA-302) to License No. DPR-66. This amendment to the Unit 1 license was approved by the NRC on July 19, 2006.3.1.25 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 1.3.1.26 Engineering Change Package No. ECP-04-0440, Extended Power Uprate.3.1.27 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure 1/2-ODC-3.03 to update the alarm setpoints of [RM-I VS-i 10] and[RM-1GW-109] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275. Beaver Valley Power Station ProceroNumer: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 3.2 Commitments 3.2.1 10 CFR Part 20, Standards for Protection Against Radiation 3.2.2 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities
3.2.3 40CFR
Part 141 3.2.4 40 CFR Part 190, Environmental Radiation Protection Standards For Nuclear Power Operations.
3.2.5 Regulatory
Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I, Revision 1, October 1977 3.2.6 Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Efifuents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977 3.2.7 Regulatory Guide 1.113, Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix 1, April 1977 3.2.8 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978 3.2.9 NUREG-0737, Clarification of TMI Action Plan Requirements, October 1980 3.2.10 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)3.2.11 NUREG-1431, Standard Technical Specifications -Westinghouse Plants Specifications 3.2.12 NUREG-0800, Standard Review Plan, Postulated Radioactive Releases Due to Liquid-Containing Tank Failures, July 1981 A 3:2.13 Licensee Response to NRC Unresolved Item 50-334/83-30-05. The Radiation Monitor Particle Distribution Evaluation showed that the Licensee must continue to use correction factors to determine particulate activity in samples obtained from the effluent release pathways. Beaver Valley Power Station Proc eN. DC 3 e 0 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 7 of 79 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 The numbering of each specific ODCM Control, ODCM Surveillance Requirement and ODCM Table contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Control, ODCM Surveillance Requirement and ODCM Table numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with hnumbering changes.5.2 The numbering of each specific ODCM Report contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Report numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the charge 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 setpoint calculation.(3. 2 0)6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0 1 00(3- 18)and .1/2-ADM-1640.(3.1.7) 6,1.2 Pending changes to this procedure shall be provided to applicable station groups. For example, IF Control 3.11.1.1 is being changed, THEN the proposed changes shall be provided to the applicable station groups (i.e.; owner of the procedures), identified in the MATRIX of ODCM procedure 1/2-ODC-1.01. This will allow the station groups to revise any affected procedures concurrent with the ODCM change.(3.114) 6.1.3 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001 (3.1-9) and 1/2-ADM-1640.(3!7)
7.0 PREREQUISITES
7.1 The user of this procedure shall be familiar with ODCM structure and content. Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 8 o 79 8.0 PROCEDURE 8.1 See ATTACHMENT A for a Table of Operational Modes and a Table of Frequency Notation.8.2 See ATTACHMENT B for a list of defined terms used throughout the ODCM.8.3 See ATTACHMENT C thru ATTACHMENT S for a complete description of all ODCM Controls.8.4 See ATTACHMENT T for a description of the Annual Report required by the REMP Controls.8.5 See ATTACHMENT U for a description of the Annual Report required by the RETS Controls.-END -AO Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number 4 9 of 79 ATTACHMENT A Page I of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.1 OPERATIONAL MODES MODE 1. Power Operation 2. Startup 3. Hot Standby 4. Hot Shutdown 5. Cold Shutdown 6. Refueling(2) REACTIVITY % RATED CONDITION, Keff THERMAL POWER')>0.99 >5%_>0.99 5%<0.99 0<0.99 0 AVERAGE COOLANT TEMPERATURE 3500F_350 0 F>350 0 F 350OF >Tavg>200°F<200 0 F<1I40°F<0.99<0.95 0 0 (1) Excluding decay heat.(2)' Reactor vessel head unbolted or removed and fuel in the vessel. Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: ODCM: Controls for RETS and REMP Programs Unit: Level Of Use: 1/2 General Skill Reference----- ---F Revision: Page Number: 4 1 10 of 79 ATTACHMENT A Page 2 of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY TABLE 1.2 FREQUENCY NOTATION NOTATION NOTATION D W M Q SA R S/U P N.A.FREQUENCY At. least once per 12 hours At least once per 24 hours At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 18 months Prior to each reactor startup Completed prior to each release Not applicable p F Beaver Valley Power Station ProcureNumber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 11 of 79 ATTACHMENT B Page 1 of 3 ODCM CONTROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.ACTION shall be those additional requirements specified as corollary statements to each principal CONTROL and shall be part of the CONTROLS.CHANNEL CALIBRATION shall be the adjustment, as-necessary, of the channel outputt such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions. FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior.1o release to the environment. MEMBER(S) OF THE PUBLIC (10 CFR 20 and/or 10 CFR 50) means any individual except when that individual is receiving an occupational dose. This definition is used to show compliance to ODCM CONTROL 3.11.1.1, 3.11.1.4, 3.11.2.1 and 3.11.2.5 that are based on 10 CFR Part 20. This definition is also used to show compliance to ODCM Controls 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3 and 3.11.2.4 that are based on 10 CFR Part 50.MEMBER(S) OF THE PUBLIC (40 CFR 190) means any individual that can receive a radiationdose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. However, an individual is not considered a MEMBER OF THE PUBLIC during any period in which he is engaged in carrying out any operation which is part of the nuclear fuel cycle. This definition is used to show compliance to an ODCM CONTROL 3.11.4.1 that is based on 40 CFR Part 190.: Procedure Number: BeavyPower Station i: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 1 21 of 79 i ATTACHMENT B Page 2 of 3 ODCM CONTROLS: DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required, by Technical Specification (TS) Section 6.8.6 and (2) descriptions of the information that: should: be included inf the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release RePorts that are also required by the Administrative Controls Section of the TS OPERABLE/OPERABILITY A system, subsystem, train, component, or device'shall be OPERABLE or have'OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related safety function(s). OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in ATTACHMENT A Table 1.1.PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement. RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2689 MWt.REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.SHUTDOWN means reactor powe change to 0% power.SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. The Figure for Liquid Effluent Site Boundary is contained in 1/2-ODC-2.01. The Figure for Gaseous Effluent Site Boundary is contained in 1/2-ODC-2.02. STARTUP means reactor power change from 0% power.SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source..THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNRESTRICTED AREA means any area access to which is neither limited nor controlled by the licensee. Procedure Number: yPower Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 13 of 79 ATTACHMENT B Page 3 of 3 ODCM CONTROLS: DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas'effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered -to be VENTILATION EXHAUST TREATMENT'SYSTEM components. VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a-manner that replacement air or. gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. Procedure Number: Beaver Valley Power Station o /2-ODC-3.03mJ Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number:________ 4___ 14of7 ATTACHMENT C Page 1 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: APPLICABILITY
3.0.1 Compliance
with the ODCM CONTROLS in the succeeding ODCM CONTROLS is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the ODCM CONTROL, the associated ODCM ACTION requirements shall be met, except as provided in ODCM CONTROL 3.0.6.3.02 Non-compliance with a ODCM CONTROL shall exist when the requirements of the ODCM CONTROL and associated ODCM ACTION requirements are not met within the specified time intervals. If the ODCM CONTROL is restored prior to expiration of the specified time intervals, completion of the ODCM ACTION requirements is not required.3.03 When a ODCM CONTROL is not met (except as provided in the associated ODCM ACTION requirements) within one hour, action shall be initiated to place the unit in a MODE in which the ODCM CONTROL does not apply by placing it, as applicable, in: 1. At least HOT STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within the subsequent 24 hours.Where corrective measures are completed that permit operation under the ODCM ACTION requirements, the ODCM ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the ODCM CONTROL. Exceptions to these requirements are stated in the individual ODCM CONTROLS.3.0.4 When an ODCM CONTROL is not met, entry into an OPERATIONAL MODIE or specified condition in the Applicability shall only be made: a. When the associated ODCM ACTIONS to be entered permit continued operation in the OPERATIONAL MODE or other specified condition in the Applicability for an unlimited period of time, or b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the OPERATIONAL MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions, to this ODCM CONTROL are stated in the individual ODCM CONTROLS, or c. When an allowance is stated in the individual value, parameter, or other ODCM CONTROL.( Beaver Valley Power Station Procedure NumbCr: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 15 of 79 ATTACHMENT C.Page 2 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS This ODCM CONTROL shall not prevent changes in OPERATIONAL MODES or other specified conditions in the Applicability that are required to comply with ODCM ACTIONS or that are part of a shutdown of the unit.3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable,', it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable ODCM Control;for Operation, provided; (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its :redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied within 2 hours, action shall be initiated to place the unit in a MODE in which the applicable ODCM CONTROL does not apply, by placing it, as applicable, in: I. At least HOT STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within the subsequent 24 hours This ODCM CONTROL is not applicable in MODES 5 or 6.3.0.6 Equipment removed from service or declared inoperable to comply with ODCM ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other. equipment. This is an exception to ODCM CONTROL 3.0.1 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. Procedure Number: Beaver Valley Power Station 1/2-ODc-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 16 of 79 ATTACHMENT C Page 3 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: SURVEILLANCE REQUIREMENTS
4.0.1 Surveillance
Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual ODCM CONTROLS unless otherwise stated in an individual ODCM Surveillance Requirement. -Failure to meet a ODCM Surveillance, whether such failure is experienced during the performance of the Surveillance or between performance of the Surveillance, shall be failure to meet the ODCM CONTROL. Failure to perform a Surveillance within the allowed surveillance interval, defined by ODCM Surveillance Requirement 4.0.2, shall be failure to meet the ODCM CONTROL except as provided in ODCM Surveillance Requirement
4.0.3. Surveillances
do not have to be performed on inoperable equipment or variables outside specified limits.4.02 Each ODCM Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the ODCM surveillance interval.4.0.3 If it is discovered that a ODCM Surveillance was not performed within its allowed ODCM surveillance interval (defined by ODCM Surveillance Requirement 4.0.2), then compliance with the requirement to declare the ODCM CONTROL not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified surveillance interval, whichever is greater. This delay period is permitted to allow performance of the ODCM Surveillance. A risk evaluation shall be performed for any ODCM Surveillance delayed greater than 24 hours and the risk impact shall be managed.If the ODCM Surveillance is not performed within the delay period, the ODCM CONTROL must immediately be declared not met, and the applicable ODCM ACTION(s) must be entered.When a ODCM Surveillance is performed within the delay period and the ODCM Surveillance is not met, the ODCM CONTROL must immediately be declared not met, and the applicable ODCM ACTION(s) must be entered.4.0.4 Entry into an OPERATIONAL MODE or other specified condition in the Applicablity of a ODCM CONTROL shall only be made when the ODCM Surveillances have been met within their allowed surveillance interval, except as provided by ODCM Surveillance Requirement 4.0.3. When a ODCM CONTROL is not met due to Surveillances not having been met, entry into an OPERATIONAL MODE or other specified condition in the Applicability shall only be made in accordance with ODCM CONTROL 3.0.4. This provision shall not prevent entry into OPERATIONAL MODES or other specified conditions ih the Applicability, that are required to comply with ODCM ACTION requirements or that are part of a shutdown of the unit.( .. Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 17 of 79 ATTACHMENT D Page 1 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION CONTROLS: RADIATION MONITORING (HIGH RANGE INSTRUMENTATION) 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.APPLICABILITY: As shown in Table 3.3-6.ACTION: a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in ODCM Control 3.3.3.1, Table 3.3-6, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable.
- b. With one or more radiation monitoring channels inoperable, take the ACTION shown in ODCM Control 3.3.3.1, Table 3.3-6.c, The provisions of ODCM Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in ODCM Control 3.3.3.1, Table 4.3-3. Beaver Valley Power Station Procedure Number: 1 /2-ODC-3 .03 4, Title: ODCM: Controls for RETS and REMP Programs Unit: Level Of Use: 1/2 I General Skill Reference. -'-- !- ,,i t Revision: -Page Number 4 1 19of 79 L I ATTACHMENT D Page 2 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 BV-I RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a) MINIMUM NOMINAL CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT<') RANGE ACTION 1. Noble Gas Effluent Monitors -SPINGS t 4)a. Reactor BuildingISLCRS (CV-1; Also called Elevated Release)Mid Range Noble Gas (1) 1,2,3,&4 Pri: (RM-IVS-I1OCh 7)1st PMM: (RM-IVS-I12 SA-10)2nd PMM: (RM-IVS-107B, or 110 Ch 5)3rd PMM: Grab Sampling every 12 hours 35: 1660 cmp IE-3 to I E+3 uCi/cc(2)High Range Noble Gas (1)Pri: (RM-IVS-I10 Ch 9)1st PMM: (RM-IVS- 112 SA-9 2nd PMM: (RM-IVS-107B, or I 10 Ch 5)3rd PMM: Grab Sampling every 12 hours 1,2,3, & 4 35 35 NA IE-1 to IE+5 uCi/cc(2)A b. Auxiliary Building Ventilation System (VV-I; Also called Ventilation Vent)Mid Range Noble Gas (1) 1, 2,3, & 4 Pri: (RM-IVS-109 Ch 7) < 1390 cpm Ist PMM: (RM-IVS-I 1 SA-10)2nd PMM: (RM-IVS-101B, or 109 Ch 5)3rd PMM: Grab Sampling every 12 hours High Range Noble Gas (1) 1, 2,3, & 4 Pri: (RM-IVS-109 Ch 9) NA Ist PMM: (RM-I VS-Ill SA-9)2nd PMM: (RM-IVS-101B, or 109 Ch 5)3rd PMM: Grab Sampling every 12 hours 35 IE-3 to I E+3 uCi/cc(2)35 IE-1 to IE+5 uCi/cc(2)c. Gaseous Waste/Process Vent System (PV-1/2)Mid Range Noble Gas (1) 1, 2, 3, & 4 Pri: (RM-IGW-109 Ch 7)lst.PMM: (RM-IGW-110 SA-10)2na PMM: (RM-IGW-108B, or 109 Ch 5)3rd PMM: Grab Sampling every .12 hours Hizh Ranae Noble Gas (1) 1, 2, 3, & 4 Pri: (RM-IGW-109Ch9) 1stPMM: (RM-IGW-IIOSA-9) 2nd PMM: (RM-IGW-108B, or 109 Ch5)3rd PMM: Grab Sampling every 12 hours 35 NA 1E-3 to I E+3 uCi/cc(3)35_< 1.76E+5 IE-1 to IE+5 uCi/cc(3)(a)Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN_the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days. Beaver Valley Power Station Procedure Numbe: 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 19 of79 ATTACHMENT D Page 3 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued) BV-I RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM Preplanned Method of Monitoring(a) MINIMUM *CHANNELS APPLICABLE OPERABLE MODES NOMINAL MEASUREMENT RANGE INSTRUMENT SETPOINT)'I ACTION 2. Noble Gas Effluent Steam Monitors a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-IMS-100A) (1) 1, 2, 3, & 4 < 50 cpm PMM: (Form l/2-HPP-4.02.009.FOI) Pri: (RM-1MS-I00B) (1) 1,2,3, & 4 _< 50 cpm PMM: (Form I/2-HPP-4.02.009.FO1) I E- 1 to I E+3 uCi/cc IE-i to IE+3 uCi/cc IE-1 to 1E+3 uCi/cc 35 35 35 35 Pri: (RM-1MS-100C) (1) 1, 2,3, & 4 PMM: (Form I/2-HPP-4.02.009.F0I)
- b. Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101)
(1) i, 2,3,&4 PMM: (Form l/2-HPP-4.02.009.FOI) < 50 cpm< 170 cpm I E- I to IE+3 uCi/cc (a) Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days. Beaver Valley Power Station Procedure Number:~eave 1 /2-ODC-3 .03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: p ATTACHMENT D Page 4 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued) BV-2 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a) MINIMUM CHANNELS OPERABLE APPLICABLE MODES NOMINAL .MEASUREMENT RANGE INSTRUMENT SETPOINT<') ACTION 1. Noble Gas Effluent Monitors a. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)Midranve Noble Gas (Xe-133 , Pri: (2HVS-RQ 109C) (1)1st PMM: (2HVS-RQI09D) 2nd PMM: (2HVS-RQl09B) 3rd PMM: Grab Sampling every 12 hours High Ranze Noble Gas (Xe-133)Pri: (2HVS-RQ109D) (1)1st PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours 1,2,3, & 4 1, 2,3,&4 NA NA IE-4 to IE+2 ltCi/cc 35 IE-I to IE+5 pCi/cc 35 (a Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days. Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 21 of 79 ATTACHMENT D Page 5 of 8.ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued) TABLE NOTATIONS Above background (2) Nominal range for Ch 7 and Ch 9. The Alarm in set on Ch 7.(3) Nominal range for Ch 7 and Ch 9. The Alarm in set on Ch 9.(4) Other SPING-4 channels are not applicable to this ODCM Control.ACTION STATEMENTS ACTION 35 With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours, or: a) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and b) Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. IPocedure Number: Beaver Valley Power Station 1r2-ODC-3.03 !Title: Unit: 1/2 SLevel Of Use: General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 1 22 of79 I IF ATTACHMENT D Page 6 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued) BV-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instrument PMM = Preplanned Method of Monitorin CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION
- 1. Noble Gas Effluent Monitors -SPINGS a. Reactor Building/SLCRS (CV-I; Also called Elevated Release)Mid Range Noble Gas S R Pri: (RM-IVS-1 10 Ch 7)1st PMM: (RM-IVS-112 SA-10)2nd PMM: (RM-IVS-107B, or VS-I 10 Ch 5)3rd PMM: Grab Sampling every 12 hours High Range Noble Gas S R Pri: (RM-IVS-llOCh9)
Ist PMM: (RM-IVS-112 SA-9)2nd PMM: (RM- I VS- 107B, or VS- I 10 Ch 5)3rd PMM: Grab Sampling every 12 hours b. Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)Mid Range Noble Gas S R Pri: (RM-IVS-109 Ch 7)1st PMM: (RM-IVS-l 11 SA-10)2nd PMM: (RM-IVS-10 1B, or VS- 109 Ch 5)3rd PMM: Grab Sampling every 12 hours TEST M M M M g(a)MODES IN WHICH SURVEILLANCE REQUIRED 1, 2,3,&4 1,2,3, & 4 1, 2,3,&4 1, 2, 3, & 4 1, 2,3,&4 1, 2,3,&4 High Range Noble Gas Pri: (RM-IVS-109 Ch 9)1st PMM: (RM-I VS- 11 SA-9)2nd PMM: (RM-IVS-101B, or VS-109 Ch 5)3rd PMM: Grab Sampling every 12 hours c. Gaseous Waste Process Vent System (PV-1,2)Mid Range Noble Gas Pri: (RM-IGW-109 Ch 7)1st PMM: (RM-IGW-1 10 SA-10)2nd PMM: (RM-IGW-108B, or GW-109 Ch 5)3rd PMM: Grab Sampling every 12 hours High Range Noble Gas Pri: RM-IGW-109 Ch 9)1st PMM: (RM-IGW-1 10 SA-9)2nd PMM: (RM-IGW-108B, or GW-109 Ch5)3rd PMM: Grab Sampling every 12 hours S R S R M S R M (a)Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance " of the primary instrument exceeds 30 days. Beaver Valley Power Station Procedure Number: v 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 23 of 79 ATTACHMENT D Page 7 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued) BV-I RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a) CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 2. Noble Gas Effluent Steam Monitors a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-IMS-100A) S R M 1, 2, 3, & 4 PMM: (Form l/2-HPP-4.02.009.FOI) Pri: (RM-IMS-100B) S R M 1,2,3,&4 PMM: (Form I/2-HPP-4.02.009.FO l)Pri: (RM-IMS-100C) S R M 1, 2, 3, & 4 PMM: (Form 1/2-HPP-4.02.009.FO I)b. Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101) S R M 1, 2, 3, & 4 PMM: (Form I/2-HPP-4.02.009.FOI)(a) Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days. Beaver Valley Power Station Procedure Number/2ODC3.03 Title: Unit: Level Of Use: General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: ATTACHMENT D Page 8 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued) BV-2 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a) CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 1. Noble Gas Effluent Monitors a. SLCRS Unfiltered Pathway (CV-2; Also called Elevated Release)Mid Ranee Noble Gas S R M 1, 2,3, & 4 Pri: (2HVS-RQ109C) 1st PMM: (2HVS-RQl09D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours Hizh Range Noble Gas S R M 11 2,3, & 4 Pri: (2HVS-RQ1I09D) ist PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours (a) Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.* ..,. .... Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 2-5 of 79 ATTACHMENT E Page 1 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FORLIQUID EFFLUENTS CONTROLS: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.9 In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive liquid effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.9, Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of ODCM CONTROL 3.11.1.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with 1/2-ODC-2.01.Applicability: During releases through the flow path.Action: a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or correct the alarm/trip setpoint.b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in ODCM Control 3.3.3.9, Table 3.3-12 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.c. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.9, Table 4.3-12. Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 1 Title: Unit: Level Of Use: 1 2 General Skill Reference ODCM: Controls for RETS and REMP Programs JRevision: Page Number: ATTACHMENT E Page 2 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE33-12 BV-I RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt Alternate Instruments MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1. Gross Activity Monitors Providing Automatic Termination Of Release a. Liquid Waste Effluents Monitor (1) 23 Pri: (RM-1LW-104)
- b. Liquid Waste Contaminated Drain Monitor (1) 23 Pri: (RM-1LW-116)
- c. Auxiliary Feed Pump Bay Drain Monitor (1) 24 Pri: (RM-IDA-100)
- 2. Gross Activity Monitors Not Providing Termination Of Release a. Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Water Monitor Pri: (RM- 1RW-l 00)3. Flow Rate Measurement Devices a Liquid Ralwaste Efflutet line (1) 25 Pfi: (FR-ILW-104) for (RM-1LW- 104)b. Liquid Waste Contaminated Drain Line (1) -25 Pri: (FR-1LW-103) for (RM-ILW- 116)c. Cooling Tower Blowdown Line (1) 25 Pri: (FT-1CW-101-1) or.Alt (FT-1CW-101) and:(2CWS-FTl01)
- 4. Tank Level Indicating Devices (for tanks outside plant building)a. Primary Water Storage Tank (1) 26 Pri: (LI- l PG- 115A) for (1BR-TK-6A)
- b. Primary Water Storage Tank (1) 26 Pri: (LI- IPG-I 15B) for (IBR-TK-6B)
- c. Steam Generator Drain Tank (1) 26 Pri: (LI- I LW-I 10) for (1LW-TK-7A)
- d. Steam Generator Drain Tank (1) 26 Pri: (LI-ILW-I
- 11) for (ILW-TK-7B)
Beaver Valley Power Station ProcreoNumbr: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 27 of 79 ATTACHMENT E Page 3 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued) BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release a. Liquid Waste Process Effluent Monitor (1) 23 Pri: (2SGC-RQ!00)
- 2. Gross Radioactivity Monitors Providing Alarm But Not Providing Termination Of Release a. None Required 3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent (1) 25 Pri: (2SGC-FSIOO)
- b. Cooling Tower Blowdown Line (1) 25 Pri: (FT-1CW-101-1) or Alt: (FT-ICW-101) and (2CWS-FT101)
- 4. Tank Level Indicating Devices (for tanks outside plant buildings)
- a. None Required' Beaver Valley Power Station ProcedureNumber:
- 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number: 4 28 of 79 i ATTACHMENT E Page 4 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued) ACTION STATEMENTS: Action 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be initiated (or resumed) provided that, prior to release: 1. At least two independent samples are analyzed in accordance with ODCM SURVEILLANCE REQUIREMENT 4.11.1.1.1, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations(') and discharge valving, or 2. Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement. Otherwise, suspend release of radioactive effluents via this pathway.Action 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided: 1. That at least once per 12 hours grab samples are analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection (LLD) of at least 1 E-7 uCi/ml, or 2. Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channelshall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement. () Since the computer software used for discharge permit generation automatically performs the release rate calculations, then the independent signatures on the discharge permit for "preparer" and"reviewer" satisfy the requirement for "...two technically qualified members of the Facility Staff independently verify the release rate calculations..." 4 Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 29 of 79 ATTACHMENT E Page 5 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS Table 3.3-12 (continued) ACTION STATEMENTS Action 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided: 1. The flow rate is estimated at least once per 4 hours during actual releases. (Pump" curves may be used to estimate flow), or 2, Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement. Action 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided: 1. The tank liquid level is estimated during all liquid additions to the tank, or 2. Initiate monitoring with the 'comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement. Beaver Valley Power StationI Procedure Number: B V1/2-ODC-3.03 Title: ,Unit: Level Of Use: 11/2 General Skill Referenc ODCM: Controls for RETS and REMP Programs Revision: Page Number: I 4 30 of 79 ATTACHMENT E Page 6 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 BV-I RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL, SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release a. Liquid Radwaste Effluent Line D p(S) R(3) Q(I)Pri: (RM-I LW-104)b. Liquid Waste Contaminated D p(5) R(3) Q(1)Drain Line Pri: (RM-ILW- 116)c. Auxiliary Feed Pump Bay D D R(3) Q(1)Drain Monitor Pri: (RM- IDA- 100)2. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination Of-Release a. Component Cooling -Recirculation D M(5) R(3) Q(2)Spray Heat Exchangers River Water Monitor Pri: (RM- I RW: 100)3. Flow Rate Monitors a. Liquid Radwaste Effluent Lines D (4) NA R Q Pri: (FR-ILW-104) for (RM-ILW-104)
- b. Liquid Waste Contaminated Drain Line D(4) NA R Q Pri: (FR-ILW-103) for (RM-ILW- 116)c.' Cooling Tower Blowdown Line D(4) NA R Q Pri: (FT- ICW-101-1) or Alt: (FT-ICW-101) and (2CWS-FT101)
Beaver Valley Power Station Procedure Numbenr: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 31 of 79 ATTACHMENT E Page 7 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued) BV- 1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri6= Primary Instruments, Alt = Alternate Instruments INSTRUMENT CHANNEL CHECK S OURCE CHECK NA CHANNEL CALIBRATION R CHANNEL FUNCTIONAL TEST Q 4. Tank Level Indicating Devices (for tanks outside plant buildings)
- a. Primary Water Storage Tank D*Pri: (LI-IPG-1 15A) for (1BR-TK-6A)
- b. Primary Water Storage Tank D*Pri: (LI -IPG- 115B) for (1BR-TK-6B)
- c. Steam Generator Drain Tank D*Pri: (LI-I LW- 110) for (1 LW-TK-7A)d. Steam Generator Drain Tank D*Pri: (LI-ILW-.I
- 11) for (ILW-TK-7B)
NA NA NA R R R Q Q Q*During liquid additions to the tank. Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use:/ 1/2 General Skill ODCM: Controls for RETS and REMP Programs Revision: Page Number: ATTACHMENT E Page 8 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued) BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release a. Liquid Waste Process Effluent D p(5) R(sX 3) Q(7)Pri: (2SGC-RQIOO)
- 2. Flow Rate Measurement Devices a. Liquid Radwaste Effluent D(4) NA R Q Pri: (2SGC-FS 100)b. Cooling Tower Blowdown Line D(4) NA R Q Pri: (FT-ICW-101-1) or Alt: (FT-ICW-101) and (2CWS-FTI01)
- 3. Tank Level Indicating Devices (for tanks outside plant buildings)
- a. None Required Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number:..4 33 of 79 ATTACHMENT E Page 9 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued) TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.2. Downscale failure.3. Instrument controls not set in operate mode.(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured leVels above the alarm/trip setpoint.2. Downscale failure.3. Instrument controls are not set in operate mode.(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of (Standards/NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS/NIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages. (Existing plants may substitute previously established calibration procedures for this requirement). (4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.(5) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response. Beaver Valley Power Station P Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number:..... 4 34 of 79 1 p ATTACHMENT E Page 10 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued) TABLE NOTATION (6) The CHANNEL FUNCTIONAL TEST shall~also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs when the instrument indicates measured levels above the Alarm/Trip Setpoint.The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Alarm Annunciation occurs if any of the following conditions exists: 1. Downscale failure.2. Instrument controls are not set in operate mode.(7) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint.(8) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist: 1. Downscale failure.2. Instrument controls are not set in operate mode. Beaver Valley Power Station ProcureNumbor: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 35 of 79 ATTACHMENT F Page 1 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES CONTROLS: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3.3.3.10 In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive gaseous effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.10, Table 3.3-13 shall be operable 'With their alarm/trip setpoints set to ensure that the limits of ODCM CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with 1/2-ODC-2.02. Applicability: During releases through the flow path.Action: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of ODCM CONTROL 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm/trip setpoint.b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in ODCM Control 3.3.3.10, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.c. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.10, Table 4.3-13. Beaver Valley Power Station P1o o 2oOm C-e.0____ ____ ___ ____ ___ ____ ___ ____ ___1/2-ODC-3.03 Title: BPUnit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: ATTACHMENT F Page 2 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri Primary Instruments, Alt = Alternate Instruments MINIMUM CHANNELS NSIRUMENT .OPERABLE APPLICABILTY ACTION 1. Gaseous Waste/Process Vent System (PV-i,2)a. Noble Gas Activity Monitor (1) 27,29,30A,30B Pri: (RM- 1GW- 108B) or Alt For Continuous Release: (RM-IGW-109 Ch 5) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.Alt For Batch Releases: (See Action 27) RM-IGW-109 Ch 5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-I GWDT's or the BV-2 GWST's. Specifically, SINCE this channel.does not perform the same automatic isolation function as the primary channel, THEN ACTION 27 shall be followed for batch releases of the BV-I GWDT's or the BV-2 GWST's via this pathway.b. Particulate and Iodine Sampler (!)
- 32 Pri: (Filter Paper & Charcoal Cartridge for RM- 1GW-i109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IGW-1 10) or -2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)c. System Effluent Flow Rate Measuring Device (1)
- 28A Pri: (FR-IGW-108) or Alt: (RM-IGW-109 Ch 10)d. Sampler Flow Rate Measuring Device Used for (!)
- 28B Particulate and Iodine Sample Collection (see 1.b)Pri: (RM-IGW-109 Ch 15) or Alt: (Rotometer:
FM-IGW-101, and Vacuum Gauge: PI-IGW-135)
- 2. Auxiliary BuildingVentilation System (VV-1; Also called Ventilation Vent)a. Noble Gas Activity Monitor (1) -29,30A Pri: (RM-IVS-101B) or Alt: (RM- 1VS-109 Ch 5)b. Particulate and Iodine Sampler. ()
- 32 Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-I 09) or nst Alt: (Filter Paper& Charcoal Cartridge for RM-IVS- I1) or"nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)c.' System Effluent Flow Rate Measuring Device (1)
- 28A Pri: (FR- IVS-101) or Alt: (RM-1VS-109 Ch 10)d. Sampler Flow Rate Measuring Device Used for (I)
- 28B Particulate and Iodine Sample Collection (see 2.b)Pri: (RM-IVS- 109 Ch 15) or Alt: (Rotometer:
FM-IVS-102, and Vacuum Gauge: PI-IVS-659) (*During Releases via this pathway. Beaver Valley Power Station PoeNmberODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 37 of79 ATTACHMENT F Page 3 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments
- :
CILANNELS NSTRUMNt1 OPERABLE 3. Reactor Building/SLCRS (CV-1; Also called Elevated Release)a. Noble Gas Activity Monitor (1)Pri: (RM- IVS- 107B) or Alt: (RM-1 VS-I 10 Ch 5)b. Particulate and Iodine Sampler (1)Pri: (Filter Paper & Charcoal Cartridge for RM- I VS- 110) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS- 112) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)APP[ICABL1Y AClON 29,30A 32 c. System Effluent Flow Rate Measuring Device Pri: (FR-I VS-1 12) or Alt: (RM-IVS-1 10 Ch 10)(1)**28A 28B d. Sampler Flow Rate Measuring Device Used for (1 Particulate and Iodine Sample Collection (see 3.b)Pri: (RM-IVS-I 10 Ch 15) or Alt: (Rotometer: FM-IVS-103, and Vacuum Gauge: PI-IVS-660) )*During Releases via this pathway. Procedure Number: Beaver Valley Power Station l/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 3 f7 ATTACHMENT F Page 4 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MNIMUM CHANNELS INSTRUMEN ..f OPERABLE APPUCABILHY ACTION 1. SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)a. Noble Gas Activity Monitor () 29,30B Pri: (2HVS-RQ0 101B)b. Particulate and Iodine Sampler (1)
- 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ 101) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor (1) 28A Pri: (Monitor Item 29 for 2HVS-VP 101)d. Sampler Flow Rate Monitor Used for Particulate (1) 28B and Iodine Sample Collection (see L.b)Pri: (2HVS-FITIOI)
- 2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)a. Noble Gas Activity Monitor (1) 29, 30B Pri: (2HVS-RQ 109B)b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ 109 High Flow Path) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt; (Grab samples every 12 hours)c. Process Flow Rate Monitor (1) 28A Pri: (Monitor Item 29 for 2HVS-FR22) or 1st Alt: (2HVS-F122A and F122C) or 2nd Alt: (2HVS-F122B and F122D)d. Sampler Flow Rate Monitor Used for Particulate
(!)
- 28B and Iodine Sample Collection (see 2.b)Pri: (Monitor Items 28 and 72 for 2HVS-DAU 1091B)3. Decontamination Building Vent (DV-2)a. Noble Gas Activity Monitor (1) 29 Pri: (2RMQ-RQ301B)
- b. Particulate and Iodine Sampler (I) 32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ30
- 1) or 1st Alt: (Continuous collection via RASP Pump)2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor None None None d. Sampler Flow Rate Monitor Used for Particulate (1)
- 28B and Iodine Sample Collection (see 3.b)Pri: (2RMQ-FIT301)
- During Releases via this pathway.
Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 39 of 79 ATTACHMENT F Page 5 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt= Alternate Instruments CHANNELS INS'IRUMENT " OPERABLE APPfLjABKIHY ACTION 4. Condensate Polishing Building Vent (CB-2)a. Noble Gas Activity Monitor (1)
- 29 Pri: (2HVL-RQ 112B)b. Particulate and Iodine Sampler (1)
- 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ 112)1st Alt: (Continuous collection via RASP Pump)2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor None None None d. Sampler Flow Rate Monitor Used for Particulate (1)
- 28B and Iodine Sample Collection (see 4.b)Pri: (2HVL-FIT 112)5. Waste Gas Storage Vault Vent (WV-2)a. Noble Gas Activity Monitor (1)
- 29 Pri: (2RMQ-RQ303B)
- b. Particulate and Iodine Sampler (1)
- 32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) 1st Alt: (Continuous collection via RASP Pump)2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor None None None d. Sampler Flow Rate Monitor Used for Particulate (1)
- 28B and Iodine Sample Collection (see 5.b)Pri: (2RMQ-FIT303)
- During Releases via this pathway.
Beaver Valley Power Station Procedure N/e2- 3: Title: Unit: ' Level Of Use: General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1I 4 I 40 of 79 I ATTACHMENT F Page 6 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) ACTION STATEMENTS Action 27 APPLICABLE FOR BATCH RELEASES OF BV-I GASEOUS WASTE DECAY TANKS OR BV-2 GASEOUS WASTE STORAGE TANKS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the Unit 1 Gaseous Waste Decay Tanks (GWDT's) or the Unit 2 Gaseous Waste Storage Tanks (GWST's) may be released to the environment provided that prior to initiating (or resuming) the release: 1. At least two independent samples of the tank's content are analyzed and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup, or 2. Initiate continuous monitoring with the comparable alternate monitoring channel.ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement. Otherwise, suspend releases of radioactive effluents via this pathway.Action 28A APPLICABLE FOR BV-l SYSTEM EFFLUENT FLOW RATE MEASURING DEVICES OR BV-2 PROCESS FLOWRATE MONITORS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may. continue provided: 1. The system/process flow rate is estimated at least once per 4 hours (or assumed to be at the ODCM design value l)), or 2. Initiate continuous monitoring with the comparable alternate monitoring channel.ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement.(I) In lieu of estimating the system/process flow rate at least once per 4 hours, the system/process flow rate can be assumed to be at the following ODCM design values: 1,450 cfm = BV-1 Gaseous Waste/Process Vent System (PV-1,2)62,000 cfm = BV-1 Auxiliary Building Ventilation System (VV-I) 4 49,300 cfm = BV-l Reactor Building/SLCRS (CV-1)23,700 cfm = BV-2 SLCRS Unfiltered Pathway (VV-2)59,000 cfm = BV-2 SLCRS Filtered Pathway (CV-2) Beaver Valley Power Station Procedure Number 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 41 of 79 ATTACHMENT F Page 7 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) ACTION STATEMENTS APPLICABLE FOR BV-1 SAMPLER' LOWRATE MEASURING DEVICES OR BV-2 SAMPLER FLOWRATE MONITORS Action 28B With the numberof channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided: 1. The sampler flow rate is estimated at leastonce per 4 hours, or 2. Initiate continuous monitoring with the comparable alternate monitoring channel.ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement. Action 29 APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided: 1. Grab samples (or local monitor readings)(') are taken at least once per 12 hours. If grab samples are taken; these samples are to be analyzed for gross activity within 24 hours, or 2. Initiate continuous monitoring with the comparable alternate monitoring channel.ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement. For BV-2, there are situations where the local monitor (e.g.; the RM-80) is capable of performing the intended monitoring function, but the communications are lost to the Control Room. In this case, the local monitor can be read at least'once per 12 hours in-lieu of obtaining grab samples at least once per 12 hours.(1) Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference TRtve:iUnit: PgNusber: ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 42 of 7 L ATTACHMENT F Page 8 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued) ACTION STATEMENTS Action 30A APPLICABLE FOR THE INITIAL BATCH PURGE OF THE BV-I REACTOR CONTAINMENT With the number of channels OPERABLE less than required by minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both RM-1VS-104A and B are not OPERABLE with the purge/exhaust system in service. The following should also be noted: 1. As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;immediately after reactor containment atmosphere equalization).
- 2. Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable.
Therefore, Action 29 is applicable for INOPERABLE monitors performing a continuous release of the reactor containment atmosphere. Action 30B APPLICABLE FOR THE INITIAL BATCH PURGE OF THE BV-2 REACTOR CONTAINMENT With the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both 2HVR-RQ104A and 104B are not OPERABLE with the purge/exhaust system in service. The following should also be noted: 1. As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;immediately after reactor containment atmosphere equalization).
- 2. Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable.
Therefore, Action 29 is applicable for INOPERABLE monitors when performing a continuous release of the reactor containment atmosphere. Action 32 APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided : 4 samples are continuously collected with auxiliary sampling equipment as required in ODCM Control 3.11.2.1, Table 4.11-2, or sampled and analyzed once every 12 hours. Beaver Valley Power Station ProcedureNu ODC 3 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 43 of 79 ATTACHMENT F Page 9 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 VB4-IRADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P' .Primary Pruments, Alt= Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL 'INSTRUMENT, CHECK CHECK CALIBRATION TEST 1. Gaseous WastelProcess Vent System (PV-1,2)a. Noble Gas Activity Monitor .P.p(4) R t 3 , ..')Pri: (RM-IGW-108B) Alt For Continuous Release: (RM-IGW-109 Ch 5) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.Alt For Batch Releases: (Sec Action 27): RM-IGW-109 Ch 5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-I GWDTs or the BV-2 GWST's. Specifically, SINCE this channel doesnot perform the same automatic isolation function as the primary channel, THEN ACTION 27 shall be followed for batch releases of the BV-I GWDT's or the BV-2 GWSTs via this pathway b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for RM- IGW- 109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM- IGW-110) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)c. System Effluent Flow Rate Measuring Device P NA R Q Pri: (FR-IGW-108) or Alt: (RM-IGW-109 Ch 10)d. Sampler Flow Rate Measuring Device Used for D* NA R Q Particulate and Iodine Sample Collection (see Lb)Pri: (RM-IGW-109 Ch 15) or Alt: (Rotometer: FM-IGW-101, and Vacuum Gauge: PI-IGW-135)
- 2. Auxiliary Building Ventilation'System (VV-I; Also called Ventilation Vent)a. Noble Gas Activity Monitor D M RO) Q(2)Pri: (RM-IVS-101B) or p(4)***Alt: (RM-IVS-109 Ch 5)b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for RM- I VS- 109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-! 11) or 2nd Alt: (Continuous collection via RASP Pump) or Ird Alt: (Grab samples every 12 hours)c. System Effluent Flow Rate Measurement Device D NA R Q Pri: (FR-I VS-101) or Alt: (RM-IVS-109 Ch 10)d. Sampler Flow Rate Measuring Device Used for D NA RQ Particulate and Iodine Sample Collection (see 2.b)Pri: (RM-IVS-109 Ch 15) or Alt: (Rotometer:
FM- I VS- 102, and Vacuum Gauge: P1- I VS-659)* During Releases via this pathway.*** During purging of Reactor Containment via this pathway. Beaver Valley Power Station ProcureNumber:DC3.03 1/2 I Genral Ih Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 44 of 79 ATTACHMENT F Page 10 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL.CHANNEL SOURCE, CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 3. Reactor Building/SLCRS (CV-1; Also called Elevated Release)a. Noble Gas Activity Monitor D Nri4), R(3) Q(2)Pri: (RM- IVS-107B)or p(4)***Alt: (RM-IVS-110 Ch 5)b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for RM-IVS- I10) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-1VS- 112) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)c. System Effluent Flow Rate D NA R Q j Measuring Device Pri: (FR-I VS- 112) or Alt: (RM-IVS-110 Ch 10)d. Sampler Flow Rate Measuring Device Used for D NA R Q Particulate and Iodine Sample Collection (see 3.b)Pri: (RM-IVS-I 10 Ch 15) or Alt: (Rotometer: FM-IVS-103, and Vacuum Gauge: PI-IVS-660)
- During releases via this pathway.***During purging of Reactor Containment via this pathway.A Beaver Valley Power Station ProcdureNumber:
1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 45 of 79 ATTACHMENT F Page 11 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued) BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1. SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)a. Noble Gas Activity Monitor D M0);, 0 Q(5)Pri: (2HVS-RQ 101 B) p(4)***b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ 101) or I st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor D NA R Q Pri: (Monitor Item 29 for 2HVS-VP101)
- d. Sampler Flow Rate Monitor Used for Particulate D NA R Q and Iodine Sample Collection (see 1.b)Pri: (2HVS-FIT 101)2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)a. Noble Gas Activity Monitor D M Q(S)Pri: (2HVS-RQ 109B) p(4)***b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ 109 High Flow Path) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor D NA R Q Pri: (Monitor Item 29 for 2HVS-FR22) or 1st Alt: (2HVS-FI22A and F122C) or 2nd Alt: (2HVS-F122B and F122D)d. Sampler Flow Rate Monitor Used for Particulate D NA R Q and Iodine Sample Collection (see 2.b)Pri: (Monitor Items 28 and 72 for 2HVS-DAUI09B)
- 3. Decontamination Building Vent (DV-2)a. Noble Gas Activity Monitor D M(4) R(3 X 6) Q(5)Pri: (2RMQ-RQ301B)
- b. Particulate and Iodine Sampler W NA NA NA Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ301) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor NA NA NA NA d. Sampler Flow Rate Monitor Used for Particulate D NA R Q and Iodine Sample Collection (see 3.b)Pri: (2RMQ-FIT301)
Beaver Valley Power Station Procedure Number: Title: Uni t: Level Of Use: RGeneral Skill Referenc 1 ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 1 46 nff 79 ATTACHMENT F Page 12 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued) BV-2 RADIOACTIVE GASEOUS EFFLUENT. MONITORING-INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANIN INSTRUMENT CHEC 4. Condensate Polishing Building Vent (CB-2)a. Noble Gas Activity Monitor D Pri: (2HVL-RQ I 12B)b. Particulate and Iodine Sampler W Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ 112) or 1 st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate .Monitor NA d. Sampler Flow Rate Monitor Used for Particulate D and Iodine Sample Collection (see 4.b)Pri: (2HVL-FIT 112)5. Waste Gas Storage Vault Vent (WV-2)a. Noble Gas Activity Monitor D Pri: (2RMQ-RQ303B)
- b. Particulate and Iodine Samples W Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)c. Process Flow Rate Monitor NA d. Sampler Flow Rate Monitor Used for Particulate D and Iodine Sample Collection (see 5.b)Pri: (2RMQ-FIT303) 4EL SOURCE CHANNEL K CHECK CALIBRATION M04) R(3 X 6)NA NA NA&1(4)NA NA NA NA NA R R(3 X 6)NA NA-R CHANNEL FUNCTIONAL TEST Q(S)NA NA Q (4 Q(S)NA NA Q Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number: 4 47 of 79 ATTACHMENT F Page 13 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued) TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alari/trip setpoint.b. Downscale failure.c. Instrument controls not set in operate mode.(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alarm/trip setpoint.b. Downscale failure.c. Instrument controls not set in operate mode.(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified be National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages.(4) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the~existing count rateto verify channel response.(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint.(6) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist: 1. Downscale failure.2. Instrument controls are not set in operate mode. Beaver Valley Power Station Procdure Nm_/2-ODC-3.03 Title: Unit: Level Of Use: onse when the channel s 112 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4_48.of_79 P ATTACHMENT G Page 1 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION CONTROLS: LIQUID EFFLUENT CONCENTRATION 3.11.1.1 In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Items 2 and 3, the concentration of radioactive material released at any time from the site (see 1/2-ODC-2.01, Figure 5-1) shall be limited to 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20.2401), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. This is referred to as the ODCM Effluent Concentration Limit (OEC). For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uCi/ml total activity.Applicability: At all times.Action: a. With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore the concentration within the above limits, and b. Submita Special Report to the Commission within 30 days in accordance with 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
- c. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of ODCM Control 3.11.1.1, Table 4.11-1 *.4.11.1.1.2 The results of radioactive analysis shall-be used in accordance with 1/2-ODC-2.01 to assure that the concentration at the point ,of release are maintained within the limits of ODCM CONTROL 3.11. 1. 1.4.11.1.1.3 When BV- 1 primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours to ensure that the Turbine Building Sump concentration does not exceed I OEC. Once it is determinedithat an OEC is reached, the Turbine Building Sump shall be routed to the Chemical Waste Sump.I Beaver Valley Power Station ProdureNu:ODC 3 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 49 of 79 ATTACHMENT G Page 2 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4 4.11.1.1.5 When BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours to ensure that the Turbine Building Sump concentration does not exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to Steam Generator blowdown hold tank (2SGC-TK21A or 2SGC-TK21B). Prior to the BV-2 Recirculation Drain Pump(s) (2DAS-P215A/B) discharging to catch basin 16, a grap sample will be taken. The samples will be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml. Water volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.* Radioactive liquid discharges are normally via batch modes. BV-I and BV-2 Turbine Building Drains shall be monitored as specified in ODCM SURVEILLANCE REQUIREMENT 4.11. 1.1.3 and 4.11.1.1.4. The BV-2 Recirculation drain pump discharge shall be monitored as specified in ODCM SURVEILLANCE REQUIREMENT 4.11.1.1.5, respectively. Beaver Valley Power Station Procdure Number: I I 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference. Revision: Page Number: 4 10 nf 79 ODCM: Controls for RETS and REMP Programs ATTACHMENT G Page 3 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11i1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER MINIMUM TYPE OF LIMIT OF LIQUID SAMPLING ANALYSIS ACTIVITY DETECTION RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (LLD)(uCi/ml)(a) A. Batch Waste P P Principal Gamma 5E-7 Release Tanks(d) Each Batch(h) Each Batch(h) Emitters(f) 1-131 IE-6 P M Dissolved And 1E-5 One Entrained Gases Batch/M(h) (Gamma Emitters)P M H-3 IE-5 Each Batch0) Composite(b) Gross Alpha IE-7 P Q Sr-89, Sr-90 5E-8 Each Batch 0') Composite(b) Fe-55 IE-6 B. Continuous Grab Sample(g) W Principal Gamma 5E-7 Releases e)(g) Composite(c) .Emitters(f) 1-131 1E-6 Grab Sample(g) M Dissolved And 1E-5 Entrained Gases (Gamma Emitters)Grab Sample(g) M H-3 1E-5 Composite(') Gross Alpha 1E-7 Grab Sample g) Q Sr-89, Sr-90 5E-8 Composite(c) Fe-55 IE-6 (I (b I Beaver Valley Power Station ProcureNumber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 51 of 79 ATTACHMENT G Page 4 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-1 (continued) TABLE NOTATION (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%:probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation): LLD = 4.66 Sb (E)(V)(2.22)(Y) exp(-XAT)where: LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);E is the counting efficiency (as counts per transformation); V is the sample size (in units of mass or volume);2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable); X is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and AT should be used in the calculations. The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Beaver Valley Power Station Procedure N.mber.OC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4,2, 7 ATTACHMENT G Page 5 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-i (continued) TABLE NOTATION (b) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.(c) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.(d) A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.(e) A continuous release exists when the discharge of liquid wastes is from a non-discrete volume;e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building Drains and the AFW Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).(0 The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported..Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides Which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.(g) When radioactivity is identified in the secondary system, a RWDA-L should be prepared on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River.(h) Whenever the BV-2 Recirculation Drain Pump(s) are discharging to catch basin 16, :sampling will be performed by means of a grab sample taken every 4 hours during pump operation. -I Procedure Number: Beaver Valley PowerStatin___o___em___ yPower Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 53 of 79 ATTACHMENT H Page 1 of I ODCM CONTROLS: LIQUID EFFLUENT DOSE CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV- I and BV-2 Technical Specification 6.8.6a, Items 4 and 5, the dose or dose commitment to MEMBER(S) OF THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see 1/2-ODC-2.01 Figure 5-1) shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.Applicability: At all times.Action: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases, and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act).*b. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11-.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with 1/2-ODC-2.01 at least once per 31 days.* Applicable only if drinking water supply is taken from the receiving water body within three miles of the plant discharge (three miles downstream only). Beaver Valley Power Station PUnrod: NOmbOr:.- Title: Level Of Use: 12 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 54 of 7 ATTACHMENT I Page 1 of 1 ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM 3.11.1.3 In accordance with BV- I and BV-2 Technical Specification 6.8.6a, Item 6, 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 the reactor unit (see 1/2-ODC-2.01 Figure 5-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.Applicability: At all times.Action: a. With liquid waste being discharged without treatment and exceeding the limits specified, prepare and submit to the Commission within 3Q days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) a Special Report which includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability.
- 2. Action(s) taken to restore the inoperable equipment to operational status, and 3. Summary description of action(s) taken to prevent a recurrence.
- b. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.01. Beaver Valley Power Station ProcdureNumber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 55 of 79 ATTACHMENT J Page 1 of I ODCM CONTROLS: LIQUID HOLDUP TANKS CONTROLS: LIQUID HOLDUP TANKS 3.11.1.4 In accordance with BV-I and BV-2 Technical Specification 6.8.6c, the quantity of radioactive material contained in each of the following tanks shall be limited to the values listed below, excluding tritium and dissolved or entrained noble gases.a. < 21 Curies: IBR-TK-6A (Unit I Primary Water Storage Tank)b. < 21 Curies: IBR-TK-6B (Unit I Primary Water Storage Tank)c. < 7 Curies: ILW-TK-7A (Unit I Steam Generator Drain Tank).d. < 7 Curies: 1 LW-TK-7B (Unit I Steam Generator Drain Tank)e. < 5 Curies: 1QS-TK-1 (Unit I Refueling Water Storage Tank-RWST)
- f. < 139 Curies: 2QSS-TK21 (Unit 2 Refueling Water Storage Tank-RWST)
- g. < 10 Curies: Unit I and 2 miscellaneous temporary outside radioactive liquid storage tanks.APPLICABILITY:
At all times.ACTION: a. With the quantity of radioactive material in the tank exceeding the limit, perform calculations to determine compliance to the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2. These calculations shall be performed at the nearest potable water supply, and the nearest surface water supply in the unrestricted area (i.e.; at the entrance to the Midland Water Treatment Facility). IF the limits of 10 CFR Part 20 are determined to be exceeded, THEN immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limits set forth in 10 CFR Part 20, and b. Submit a Special Report in accordance with 10 CFR 50.4 (b) (1) within 30 days and include a schedule and a description of activities planned and/or taken to reduce the contents to within the limits set forth in 10 CFR Part 20.c. The provisions ODCM Control 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1-4.1 The quantity of radioactive material contained in each of the above listed tanks (except the Unit 1 and 2 RWST's) shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.4.11.1.4.2 SINCE additions of radioactive material to the Unit l and 2 RWST's are normally made at the end of a refueling outage (i.e.; drain down of the reactor cavity back to the: RWST), THEN compliance to this limit shall be performed as follows: The quantity of radioactive material contained in the Unit I and 2 RWST's shall be determined to be within the above limit by analyzing a representative sample of the tank's contents within 7 days after transfer of reactor cavity water to the respective Unit's RWST. Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Control s for RETS and REMP Programs Revision: Page Number:I 4 -56 of 79 t m ATTACHMENT K Page 1 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1 In-accordance with BV-I and BV-2 Technical Specification 6.8:6a, Items 3 and 7, the dose rate in the unrestricted areas (see 1/2-ODC-2.02 Figure 5,1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values: a. The dose rate-limit for noble gases shall be < 500 mrem/yr to the total body and _<3000 mrem/yr to the skin*, and b. The dose rate limit, inhalation pathway only, for 1- 131, tritium and all radionuclides in particulate form (excluding C- 14) with half-lives greater than eight days shall be < 1500 mrem/yr to any organ.Applicability: At all times.Action: a. With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limits(s), and, b. Submit a Special Report to the Commission within 30 days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
- c. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with 1/2-ODC-2.02. 4.11.2'.1.2 The dose rate, inhalation pathway only, for 1-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in ODCM Control 3.11.2.1, Table 4.11-2.*During containment purge the dose rate may be averaged over 960 minutes. Procedure Number: Beaver Valley Power Station I/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 57 of 79 ATTACHMENT K Page 2 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE LOWER LIMIT OF GASEOUS SAMPLING ANALYSIS OF DETECTION RELEASE FREQUENCY FREQUENCY ACTIVITY ..(LLD)TYPE ._ _ _ _ _ ANALYSIS (uCi/ml)(a) A. Waste Gas Storage P P: Principal 1E-4 Tank Each Tank Each Tank. Gamma Grab Sample Emitters (g)Each Tank* Each Tank* H-3* IE-6 Grab Sample B. Containment Purge P P Principal Gamma 1E-4 Each Purgerb) Each Purge( b) Emitters(g) Grab Sample H-3 IE-6 C. Ventilation M(b)(c)(e) M(b) Principal Gamma IE-4 Systems(h) Grab Sample " Erfiiffers(g) VV-I (UI PAB/Ventilation Vent) H-3 IE-6 CV-I (Ui Rx Cont/SLCRS Vent)PV- 1/2 (U 1/2 GW/Process Vent)VV-2 (U2 SLCRS Unfiltered Path)CV-2 (U2 SLCRS Filtered Path)DV-2 (U2 Decon Bldg Vent)WV-2 (U2 Waste Gas Vault Vent)CB-2 (U2 Cond Pol Bldg Vent)* The H-3 concentration shall be estimated prior to release and followed up with an H-3 grab sample from the Ventilation System during release. Beaver Valley Power Station Procedure Nur:ODC 3 3 I Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 58 of 79 (W1 A.1 58 of 79 ATTACHMENT K Page 3 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE LOWER LIMIT OF GASEOUS SAMPLING ANALYSIS OF DETECTION RELEASE FREQUENCY FREQUENCY ACTIVITY (LLD)TYPE ANALYSIS (uCi/ml)(a) D. All Ventilation Continuoust W 1-131 IE-12 Systems Listed Charcoal 1-133 IE-10 Above (in C.) Sample Which Produce Continuous W~d) Principal Gamma 1 E- 11 Release Particulate Emitters(g) (-Sample 1-131, Others)Continuous") M Gross Alpha 1 E- I Composite Particulate Sample Continuoust 0 Q Sr-89, Sr-90 1E-l 1 Composite Particulate Sample Continuous(' Noble Gas Noble Gases I E-6 Monitor Gross Beta And Gamma (4 (9 F Procedure Number: Beaver Valley Power Station P/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number 4 59 of 79 ATTACHMENT K Page 4 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued) TABLE NOTATION (a) The Lower Limit of Detection (LLD) is defined in Table Notation (a) of ODCM Control 3.11.1. 1, Table 4.11-I for ODCM Surveillance Requirement4.11.1.1.(b) Samples (grab particulate, iodine & noble gas) and analysis shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a I hour period. This requirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.Clarification: All samples shall be obtained within 24 hours of reaching the intended steady state power level, and analyzed within 48 hours of reaching the intended steady state power level.Applicability: Unit I Ventilation Systems (VY-l, CV-I and/or PV-I/2), or Unit 2 Ventilation Systems (VV-2, CV-2 and/or PV-1/2), as appropriate. Specifically, sample the ventilation release path(s) that show a factor of 3 increase on the noble gas effluent monitor. (3.1.16) (3.1.18)(c) Tritium grab samples shall be taken at least once per 24 hours (from the appropriate ventilation release path of the refueling canal area) when the containment refueling canal is flooded. Sampling may be terminated after completion of vessel defueling. Sampling shall resume upon commencement of vessel refueling. Applicability -(Mode 6): Unit I Ventilation System (VV- I or CV- 1), or Unit 2 Ventilation System (VV-2 or CV-2), that is aligned to the Reactor Containment Building atmosphere. In lieu of sampling the ventilation release path, samples may be obtained from the Reactor Containment Building atmosphere. (3-1 -1) (3.1.19)(d) Part 1: Samples (continuous particulate & iodine) shall be changed at least once per 7 days and analyses shall be completed within,48 hours after changing, orafter removal from sampler.Applicability for Part 1: Unit I and Unit 2 Ventilation Systems (VV-I, CV-I, PV-1/2, VV-2, CV-2, DV-2, WV-2 & CB-2).Part 2: Samples (continuous particulate & iodine) shall also be changed at least once per 24 hours for at least 7 days following each SHUTDOWN, STARTUP, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period and analyses shall be completed within 48 hours of changing.When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.Clarification: All samples shall be changed within 24 hours of reaching the intended steady state power level, and analyzed within 48 hours of reaching the intended steady state power level.Applicability for Part 2: Unit 1 Ventilation Systems (VV-1, CV-1 and/or PV-l/2), or Unit 2 Ventilation Systems (VV-2, CV-2 and/or PV-l/2), as appropriate. Specifically, change out the continuous particulate, iodine samples for the ventilation release path(s) that show a factor of 3 increase on the noble gas effluent monitor. (3.1.16) (3.1.18) I Procedure Number: Beaver Valley Power StationI 1/2-ODC-3.03 Title: Unit: Level Of Use: L 12 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: I 4 I 60 of 79 ATTACHMENT K Page 5 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE (e) Tritium grab samples shall be taken at least once per 7 days (from the appropriate ventilation release path of the spent fuel pool area) whenever spent fuel is in the spent fuel pool.Applicability: Unit I Ventilation System (CV-1), or Unit 2 Ventilation System (CV-2) that is aligned to the Fuel Handling Building atmosphere. In lieu of sampling the ventilation release path, samples may be obtained from the Fuel Handling Building atmosphere. (3.1.11) (3.1.19)(f) The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM CONTROLS 3.11.2.1, 3.11.2.2, and 3.11.2.3.Clarification: The average ratio of the sample flow rate to the sampled stream flow rate can be determined, but it must not be used in dose and dose rate calculation. Specifically, use of this ratio would provide non-conservative dose calculations, and would compromise licensee response to NRC Unresolved Item 50-334/83-30-05. For information, a comprehensive three-year Radiation Monitor Particle Study was performed in response to the unresolved item's concern that the effluent monitors were not collecting representative samples per ANSI N 13.1. The results of that study concluded that a correction factor (minimum CF of 2) must be applied to particulate sample volume calculations and subsequent dose and dose rate calculations. Specifically, the minimum CF of 2 must be utilized in-lieu of actual ratios of sample flow rate to the sampled stream flow rate. In summary, the minimum CF of 2 provides adequate compensation for any negative bias in particulate sample collection. (3.2.13)Applicability: Unit I Ventilation Systems (VV-1, CV-I & PV-1/2), and Unit 2 Ventilation Systems (VV-2 &CV-2).(g) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.(h) Only when this release path is in use.Applicability: Unit I and Unit 2 Ventilation Systems (VV-l, CV-1, PV-I/2, VV-2, CV-2, DV-2, WV-2 &CB-2). Beaver Valley Power Station Procedu oNCmber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 61 of 79 ATTACHMENT L Page 1 of I ODCM CONTROLS: DOSE- NOBLE GASES CONTROLS: DOSE-NOBLE GASES 3.11.2.2 In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Items 5 and 8, the air dose from the reactor unit in unrestricted areas (see 1/2-ODC-2.02 Figure 5-1) due to noble gases released in gaseous effluents shall be limited to the following:
- a. During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation.
- b. During any calendar year, to < 10 mrad for gamma radiation and 20 mrad for beta radiation.
Applicability: At all times.Action: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission with in 30 days, pursuant to 10 CFR 20.2 203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.b. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with 1/2-ODC-2.02 at least once every 31 days. Beaver Valley Power Station t Procedure Number: 1/2-ODC-3.03 Unit: I Level Of Use: 1/2 General Skill Reference Title: ODCM: Controls for RETS and REMP Programs Revision: Page Number: A I A') nf 7Q (9 ATTACHMENT M Page I of I ODCM CONTROLS: DOSE -RADIOIODINES AND PARTICULATES CONTROLS: DOSE-RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES 3.11.2.3 In accordance with BV-l and BV-2 Technical Specification 6.8.6a, Items 5 and 9, the dose to MEMBER(S) OF THE PUBLIC from radioiodines and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) shall be limited to the following:
- a. During any calendar quarter to 7.5 mrem to any organ, and b. During any calendar year to < 15 mrem to any organ.Applicability:
At all times.Action: a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.b. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2-.3.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with 1/2-ODC-2.02 at least once every 31 days.a Beaver Valley Power Station Proc onber: C 3 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 63 of 79 ATTACHMENT N Page 1 of 1 ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM 3.11.2.4 In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Item 6, the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) when averaged over 31 days would exceed 0.3 mrem to any organ.Applicability: At all times.Action: a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which includes the following information.
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 2. Action(s) taken to restore the inoperable equipment to operational status, and 3. Summary description of action(s) taken to prevent a recurrence.
- b. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.02. Beaver Valley Power Station Procedure NubrODC 3 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: I 4 I 64 of 79 ATTACHMENT 0 Page 1 of 1 ODCM CONTROLS: GAS STORAGE TANKS CONTROLS: GAS STORAGE TANKS 3.11.2.5 In accordance with BV-I and BV-2 Technical Specification 6.8.6c, the quantity of radioactivity contained in the following gas storage tanks(s) shall be limited to the noble gas values listed below (considered as Xe-133).a. <52,000 Curies: Each BV-I Waste Gas Decay Tank (1GW-TK-1A, or 1GW-TK-IB, or 1GW-TK-1C)
- b. <19,000 Curies: Any connected group of BV-2 Gaseous Waste Storage Tanks (2GWS-TK25A thru 2GWS-TK25G)
APPLICABILITY: At all times.ACTION: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit, and b. Submit a Special Report in accordance with 10 CFR 50.4 (b)(1) within 30 days and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.c, The provisions of ODCM Control 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.5.1 For BV-I Waste Gas Decay Tanks: The quantity of radioactive material contained in each BV-I Waste Gas Decay Tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank.Performance of this surveillance is required when the gross concentration of the primary coolant is greater than 100 uCi/ml.For BV-2 Gaseous Waste Storage Tanks: The quantity of radioactive material contained in any connected group of BV-2 Gaseous Waste Storage Tanks shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tanks.'.1 Beaver Valley Power Station ProceOureNumber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 65 of 79 ATTACHMENT P Page 1 of 1 ODCM CONTROLS: TOTAL DOSE CONTROLS: TOTAL DOSE 3.11.4.1 In accordance with BV-l and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to < 75 mrems..Applicability: At all times.Action: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of ODCM CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20N.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.b. "The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM SURVEILLANCE REQUIREMENTS 4.11.1.2.1, 4.11.2.2.1, and.4.11.2.3. 1.4.11.4.1.2 Cumulative dose contributions from direct% radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with 1/2-ODC-2.04. This requirement is applicable only under conditions set forth in Actiona. of ODCM CONTROL 3.11.4.1. I Procedure Number: Beaver Valey Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: A AAnf7 ATTACHMENT Q Page I of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I 3.12.1 In accordance with BV-I and BV-2 Technical Specification 6.8.6b, Item 1, the radiological environmental monitoring program shall be conducted, as specified in ODCM Control 3.12.1, Table 3.12-1.Applicability: At all times.Action:.a. With the radiological environmental monitoring program not being conducted as specified in ODCM Control 3.12.1, Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.b. With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in ODCM Control 3.12. 1, Table 3.12.1 exceeding the limits of ODCM Control 3.12.1, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of ODCM Control 3.12.1, Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactive was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.When more than one of the radionuclides in ODCM Control 3.12.1., Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: Concentration (1) Concentration (2)Limit Level (1) + Limit Level (2) + >1.0 c. With milk or fresh leafy vegetable samples unavailable from the required number of locations selected in accordance with ODCM CONTROL 3.12.2 and listed in the ODCM, obtain replacement samples. The locations from which samples were unavailable may then be deleted from those required by ODCM Control 3.12.1, Table 3.12-1 and the ODCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
- d. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to ODC ., Control 3.12.1, Table 3.12-1 from the locations given in the ODCM and shall be analyzed pursuant to be requirements ofODCM Control 3.12.1, :Tables 3.12-1 and 4.12-1. Beaver Valley Power Station Procedure Number: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:, .Page Number: 1 4 67 of 79 AATTACHMENT Q Page 2 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCY~a) PATHWAY AND/OR SAMPLES AND COLLECTION OF ANALYSIS SAMPLE LOCATIONS FREQUENCY 1. AIRBORNE a. Radioiodine 5 locations. Continuous operation Each radioiodine canister.And Particulates "090 0 TC \l 4 of sampler with sample 1. One sample from a collection at least 'Analyze for 1-131;control location weekly.10-20 miles distant Particulate sampler.and in the least Analyze for gross prevalent wind beta weekly (b);direction Perform gamma isotopic 2. One sample from analysis on composite (by vicinity of location) sample at least community having quarterly. the highest calculated annual average ground level D/Q.2. DIRECT 40 locations Continuous Gamma dose, quarterly. RADIATION measurement with_ 2 TLDs or a pres- collection at least surized ion quarterly. chamber at each location.(a Analysis frequency same as sampling frequency unless otherwise.specified.( Particulate samples are not counted for - 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is >10 times the yearly mean of control samples.**Sample locations are given on figures and tables in 1/2-ODC-2.03. Beaver Valley Power Station ProcedCreNumer: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 68 of 79 i ATTACHMENT Q Page 3 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCy~a) PATHWAY AND/OR SAMPLES AND COLLECTION OF ANALYSIS SAMPLE LOCATIONS** FREQUENCY 3. WATERBORNE
- a. Surface 2 locations.
Composite* sample Gamma isotopic analysis of 1. One sample collected over a period composite sample by location upstream. not to exceed I month. monthly;2. One sample Tritium analysis of downstream, composite sample at least quarterly.
- b. Drinking 2 locations.
Composite* sample 1-131 analysis of each collected over a period composite sample;not to exQeed 2 -weeks.Gamma isotopic analysis of composite sample (by location) monthly;Tritium analysis of composite sample quarterly.
- c. Groundwater N/A -No wells in lower elevations between plant and river d. Sediment From 1 location.
Semi-annually. Gamma isotopic analysis Shoreline semi-annually.(a)Analysis frequency same as sampling frequency unless otherwise specified.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding two hours. For the upstream surface water location, a weekly grab sample, composited each month based on river flow at time of sampling, is also acceptable.
- Sample locations are given on figures and tables in 1/2-ODC-2.03.(I Procedure Number: Beaver Valley Power Station 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number: 1 4 69 of 29 ATTACHMENT Q.Page 4 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCY(a) PATHWAY AND/OR SAMPLES AND COLLECTION. OF ANALYSIS SAMPLE LOCATIONS** FREQUENCY.
- 4. INGESTION a. Milk 4 locationsY'.)" AtleastIbi-weeklywhen Gamma isotopic and 1-131 animals are on pasture; analysis of each sample.1. Three samples at least monthly at selected on basis of other times.highest potential thyroid dose using milch census data.2. One local large dairy.b. Fish 2 locations.
Semi-annual. One Gamma isotopic analysis on sample of available edible portions.species.c. Food Products 4 locations. Annually at time of Gamma isotopic analysis and (Leafy harvest. 1-131 analysis on edible Vegetables)
- 1. Three locations portion.within 5 miles.2. One control location.(a)Analysis frequency same as sampling frequency unless otherwise specified.(b)Othpr dairies may be included as control station or for historical continuity.
These would not be modified on basis of milch animal census.**Sample locations are given on figures and tables in 112-ODC-2.03. Beaver Valley Power Station Procedure Number: B V1/2-ODC-3.03 Title: ODCM: Controls for RETS and REMP Programs Unit: 1/2 Level Of Use: General Skill Reference Revision: 4 Page Number: 70 nf 70.ATTACHMENT Q Page 5 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE BROAD LEAF WATER PARTICULATE OR FISH MILK VEGETABLES ANALYSIS (pCi/I) GASES (pCi/m 3) (pCi/kg, WET) (pCi/I (pCi/kg, WET)H-3 2E+4(a)Mn-54 IE+3 3E+4 Fe-59 4E+2 1E+4 Co-58 IE+3 3E+4 Co-60 3 E+2 1 E+4 Zn-65 3E+2 2E+4 Zr/Nb-95 4E+2 1-131 2 (b) 0.9 3 IE+2 Cs-134 30 10 IE+3 60 IE+3 Cs-137 50 20 2E+3 70 2E+3 Ba/La-140 2E+2 3E+2 (a) For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3E'+4 pCi/I may be used.b) If no drinking water pathway exists, a value of 20 pCi/I may be used.(I a1 Beaver Valley Power Station ProceurNmber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number.4 71 of 79 ATTACHMENT Q Page 6 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 MAXIMUM VALUES FOR: THE LOWER LIMITS OF DETECTION (LLD)(a) (e)AIRBORNE PARTICULATE FOOD ANALYSIS WATER OR GAS FISH MILK PRODUCTS SEDIMENT (pCii) (ci/m 3) (pCi/kg, WET) (pCi/I) (pCi/kg, WET) (pCi/kg, DRY)Gross Beta 4 IE-2 H-3 2000()Mn-54 15 130 Fe-59 30 260 Co-58,60 15 "130 Zn-65 30 260 Zr-95 30(c)Nb-95 15(c)1-131 1 (b) 7E-2 1 60 Cs-134 15 5E-2 130 15 60 150 Cs-137 18 6E-2 150 18 80 180 Ba-140 60(c) 60 La- 140 15(c) 1 5 SProcedure Number: Beaver Valley Power Station P u 1/2-ODC-3. 0 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: ATTACHMENT Q Page 7 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1. (continued)-TABLE NOTATION (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation): LLD= 4.66 Sb (E)(V)(2.22)(Y) exp (-;XAT)where: LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);E is the counting efficiency (as counts per transformation); V is the sample size (in units of mass or volume);2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable); X, is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E,'V, Y and AT should be used in the calculations. Beaver Valley Power Station ProcduroeNumber: 1/2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 73 of 79 ATTACHMENT Q Page 8 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 (continued) TABLE NOTATION The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a mannerthat the stated LLD's will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report.(b) If no drinking water pathway exists, a value of 15 pCi/I may be used.(c) If parent and daughter are totaled, the most restrictive LLD should be applied.(d) If no drinking water pathway exists, a value of 3000 pCi/I may be used.(e) This list does not mean that only these nuclides are. to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified in the Annual Radiological Environmental Report. Beaver Valley Power Station ProcedureNumber:/2ODC 03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 4 74(o ATTACHMENT R Page 1 of 1 ODCM CONTROLS: REMP -LAND USE CENSUS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING -LAND USE CENSUS 3.12.2 In accordance with BV-I and BV-2 Technical Specification 6.8.6b, Item 2, a' land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of five miles.For elevated releases as defined in Regulatory Guide 1.111, (Rev. 1), July, 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.Applicability: At all times.Action: a. With a land use census identifying a locationi(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM SURVEILLANCE REQUIREMENT 4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the new location(s).
- b. With a land use census identifying a milk animal location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with ODCM CONTROL 3.12.1 prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the new location.
The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment. Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
- c. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey*, aerial survey, or by consulting local agriculture authorities. (* Confirmation by telephone is equivalent to door-to-door. qt-7-.Procedure Number: Beaver Valley Power Station o /2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 75 of 79 ATI'ACHMENT S Page 1 of 1 ODCM CONTROLS: REMP -INTERLABORATORY COMPARISON PROGRAM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING -INTERLABORATORY COMPARISON PROGRAM 3.12.3 In accordance with BV-I and BV-2 Technical Specification 6.8.6b, Item 3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.Applicability: At all times.Action: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.b. The provisions of ODCM CONTROL 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.12.3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report. Beaver Valley Power Station Prcedure Number: .03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: ATTACHMENT T Page 1 of 2 ODCM CONTROLS: ANNUAL REMP REPORT CONTROLS: ANNUAL REMP REPORT I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (3)6.9.2 (old TS 6.9.1. 10)The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 15 of each year.The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and in 10 CFR Part 50 Appendix I Sections IV.B.2, IV.B.3, and IV.C.The annual radiological environmental reports shall include:* Summaries, interpretations, fnd statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
- The results of the land use censuses required by ODCM CONTROL 3.12.2.* If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.* Summarized and tabulated results in the format of ODCM Control 6.9.1.10, Table 6.9-1 of all radiological environmental samples taken during the report period.In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.* A summary description of the radiological environmental monitoring program.* A map of all sampling locations keyed to a table giving distances and directions from one reactor.* uThe results of licensee participation in the Interlaboratory Comparison Program required by ODCM CONTROL 3.12.3.A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the station.(3)
Procedure Number: Beaver Valley Power Station n /2-ODC-3.03 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number.4 77 of 79 ATTACHMENT T Page 2 of 2 ODCM CONTROLS: ANNUAL REMP REPORT 4)8 00'1 S ii Ii 0 0i 0 4. 0 0x 0 I z Beaver Valley Power Station Procedure Number: Title: j Unit: 1 Level Of Use: 2 General Skill Reference ODCM: Controls for RETS and REMP Programs IRevision: P Numbe 1 4 I 78 of 79 f ATTACHMENT U Page 1 of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (4)6.9.3 The Annual Radioactive Effluent Release Report (ARERR) covering the operation of the (old TS 6.9. 1.11) unit during the previous year shall be submitted prior to May I of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I Section IV.B. 1.This report is prepared and submitted in accordance with 1/2-ENV-0 1.05, and at a minimum, shall contain the following: A summary of the quantities -of radioactive liquid and gaseous effluent and solid waste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June, 1974, "Measuring, Evaluating, And Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In: Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assessment of radiation doses shall be performed in accordance with this manual.* Any licensee initiated changes to the ODCM made during the 12 -month period.Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per ODCM CONTROLS 3.3.3.9 and 3.3.3.10.Any ODCM SURVEILLANCE REQUIREMENT deficiencies. This applies to monitoring, sampling and analysis and dose projection.
- The reasons when unusual circumstances result in LLD's higher than required by ODCM CONTROL 3.11.1.1, Table 4.11 -1 and ODCM CONTROL 3.11.2.1, Table 4.11-2.(4) A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
Beaver Valley Power Station Procedure NurODC 3 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision: Page Number: 1 4 79 of 79 ATTACHMENT U Page 2 of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT (continued)" The following information for each type of solid waste shipped offsite during the report period:-container volume-total curie quantity (determined by measurement or estimate)-principal radionuclides (determined by measurement or estimate)-type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms)-type of container (e.g., LSA, Type A, Type B, Large Quantity)-solidification agent (e.g., cement)-classification and other requirements specified by 10 CFR Part 61 0 An annual summary of hourly meteorological data collected over the previous year.This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint "frequency distributions of wind speed, wind direction, and atmospheric stability.
- An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.* An assessment of the radiation doses from radioactive effluents to MEMBER(S)
OF THE PUBLIC due to their activities inside the site boundary see 1/2-ODC-2.01 Figure 5.1 and 1/2-ODC-2.02 Figure 5-1 during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure-time, and location)shall be included in these reports. The assessment of radiation doses shall be performed in accordance with 1/2-ODC-2.04.
- An assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The SKYSHINE Code (available from Radiation Shielding Information Center, (ORNL)) is acceptable for calculating the dose contribution from direct radiation due to N-16.* If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically.}}