ML21127A165
| ML21127A165 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/17/2020 |
| From: | Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21127A168 | List: |
| References | |
| L-21-135 | |
| Download: ML21127A165 (114) | |
Text
RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-0DC-1.01 ODCM: Index, Matrix and History of ODCM Changes Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 29 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 07/17/20
Beaver Valley Power Station
Title:
ProcoduR, Number:
1/2-0DC-l.0:1 Unit:
Level OfUIICI:
l /2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Pago Number:
29 2 nf 114 TABLE OF CONTENTS 1.0
~URPOSE......................................................................................................................................... 4 2.0 SCOPE.............................................................................................................................................. 4
3.0 REFERENCES
AND COMMTTMENTS......................................................................................... 4 3.1 References Used in This Procedure........................................................................................ 4 3.2 Summary of References Used Throughout Other Procedures of the ODCM........................ 5 3.3 Commit:Inents....................................................................................................................... 15 4.0 RECORDS AND FORMS.............................................................................................................. 16 4.1 Records................ :................................................................................................................ 16 4.2 Forms.................................................................................................................................... 16 5.0 PRECAUTIONS AND LIMITATIONS........................................................................................ 16 6.0 ACCEPTANCE CRITERIA........................................................................................................... 17 7.0 PREREQUISffES.......................................................................................................................... 17 8.0 PROCEDURE................................................................................................................................. 17 8.1 Description of ODCM Structure.......................................................................................... 17 8.1.1 l/2-0DC-1.01, ODCM: Index, Matrix and History ofODCM changes............ 17 8.1.2 l/2-0DC-2.01, ODCM: Liquid Eftluents........................................................... 18 8.1.3 l/2-0DC-2.02, ODCM: Gaseous Eftluents........................................................ 19 8.1.4 l/2-0DC-2.03, ODCM: Radiological Environmental Monitoring Program...... 19 8.1.5 l/2-ODC-2.04, ODCM: Information Related to 40 CPR 190............................ 20 8.1.6 l/2-ODC-3.01, ODCM: Dispersion Calculational Procedure and Source Term Inputs................................................................................................................... 20 8.1. 7 l/2-0DC-3.02, ODCM: Bases for ODCM Controls.......................................... 20 8.1.8 l/2-0DC-3.03, ODCM: Controls for RETS and REMP Programs.................... 21 8.2 History ofODCM Changes.................................................................................................. 22 8.2.1 Change (1) ofBV-1 ODCM (Issue 1), Effective January, 1984......................... 22 8.2.2 Change (2) ofBV-1 ODCM (Issue 1, Rev 1), Effective October, 1984............. 22 8.2.3 Change (3) ofBV-1 ODCM (Issue 1, Rev 2), Effective July, 1986.................... 22 8.2.4 Change (4) ofBV-1 ODCM (Issue 2), and BV-2 ODCM (Issue 1, Rev 1),
8.2.5 8.2.6 8.2.7 8.2.8 8.2.9 8.2.10 8.2.11 8.2.12 8.2.13 8.2.14 8.2.15 8.2.16 8.2.17 Effective July, 1987............................................................................................. 23 Change (5) ofBV-1 ODCM (Issue 2, Rev 1), and BV-2 ODCM (Issue 1, Revision 2), Effective December, 1987............................................................... 24 Change (6) ofBV-1 ODCM (Issue 2, Rev 2), and BV-2 ODCM (Issue 1, Rev 3 ), Effective June, 1989....................................................................................... 24 Change (7) ofBV-1 and 2 ODCM (Issue 3), Effective August, 1995................ 26 Change (8) ofBV-1 and 2 ODCM (Issue 3, Rev 1), Effective October, 1995.... 31 Change (9) ofBV-1 and 2 ODCM (Issue 3, Rev 2), Effective May 1997.......... 34 Change (10) ofBV-1 and 2 ODCM (Issue 3, Rev 3), Effective June 1997........ 35 Change (11) ofBV-1 and 2 ODCM (Issue 3, Rev 4), Effective March 1998..... 35 Change (12) ofBV-1 and 2 ODCM (Issue 3, Rev 5), Effective November 199837 Change (13) ofBV-1 and 2 ODCM (Issue 3, Rev 6), Effective May 1999........ 38 Change (14) ofBV-1 and 2 ODCM (Rev 14), Effective March 2000................ 39 Change (15) of BV-1 and 2 ODCM (Rev 15), Effective August 2000............... 40 Change (16) ofBV-1 and 2 ODCM (Effective April 2002)................................42 Change (17) of BV-1 and 2 OCDM (Effective August 2002).............................45
Beaver Valley Power Station
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Procedure Number:
l/2-0DC-1.01 Unit Level OfUae:
1/2 General Skill Reference ODCM: Index, Matrix and History ofODCM Changes Revialon:
Page Number.
?Q 3 of 114 TABLE OF CONTENTS 8.2.18 Change (18) of the BV-1 and 2 ODCM (Effective October 2002)..................... 46 8.2.19 Change (19) ofBV-1 and 2 ODCM (Effective November 2002)....................... 47 8.2.20 Change (20) ofBV-1 and 2 ODCM (Effective October 2003)........................... 47 8.2.21 Change (21) ofBV-1 and 2 ODCM (Effective November 2004)....................... 50 8.222 Change (22) of BV-1 and 2 ODCM (Effective August 2006)............................. 53 8.2.23 Change (23) ofBV-1 and 2 ODCM (Effective December 2006)........................ 55 8.2.24 Change (24) ofBV-1 and 2 ODCM (Effective May 2007)................................. 57 8.2.25 Change (25) ofBV-1 and 2 ODCM (Effective May 2009)................................. 59 8.2.26 Change (26) ofBV-1 and 2 ODCM (Effective May 2009)................................. 64 8.2.27 Change (27) ofBV-1 and 2 ODCM (Effective August 2010)............................. 65 8.2.28 Change (28) ofBV-1 and 2 ODCM (Effective December 2010)............... '......... 69 8.2.29 Change (29) ofBV-1 and 2 ODCM (Effective January 2011)............................ 70 8.2.30 Change (30) ofBV-1 and 2 ODCM (Effective September 2011)....................... 71 8.2.31 Change (31) ofBV-1 and 2 ODCM (Effective December 2011)........................ 72 8.2.32 Change (32) ofBV-1 and 2 ODCM (Effective February 2012).......................... 72 8.2.33 Change (33) ofBV-1 and 2 ODCM (Effective June 2012)................................. 73 8.2.34 Change (34) ofBV-1 and 2 ODCM (Effective July 2012)................................. 73 8.2.35 Change (35) ofBV-1 and 2 ODCM (Effective Match 2013).............................. 74 8.2.36 Change (36) ofBV-1 and 2 ODCM (Effective March 2014).............................. 75 8.2.37 Change (37) ofBV-1 and 2 ODCM (Effective October 2014)........................... 76 8.2.38 Change (38) ofBV-1 and 2 ODCM (Effective February 2015).......................... 78 8.2.39 Change (39) ofBV-1 and 2 ODCM (Effective March 2016).............................. 79 8.2.40 Change (40) ofBV-1 and 2 ODCM (Effective November 2016)....................... 81 8.2.41 Change (41) ofBV-1 and 2 ODCM (Effective January 2017)............................ 82 8.2.42 Change (42) ofBV-1 and 2 ODCM (Effective January 2018)............................ 83 8.2.43 Change (43) ofBV-1 and 2 ODCM (Effective August 2018)............................. 84 8.2.44 Change (44) ofBV-1 and 2 ODCM (Effective April 2019)................................ 85 8.2.45 Change (45) ofBV-1 and 2 ODCM (Effective July 2019)................................. 86 8.2.46 Change (46) ofBV-1 and 2 ODCM (Effective April 2020)................................ 88 ATIACIIMENT A LIST OF ODCM TABLES...................................................................... 89 ATIACIIMENT B LIST OF ODCM FIGURES.................................................................... 95 ATTACHMENT C ODCM CONTROLS PROCEDURE MATRIX...................................... 96
Beaver Valley Power Station
Title:
Procedun, Number.
l/2-0DC-1.01 Unit l/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
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4 nf 114 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 procedme references for Radiological Effluent Technical Specifications (RETS), Radiological Environmental Monitoring Program (REMP) surveillances that were transferred from the Technical Specification Procedme 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 procedme 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 mioimire the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
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 OfRETS 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 l/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs
Beaver Valley Power Station
Title:
Procedure Number:
1/2-0DC-l.0l Unit 112 Level OfU11e:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Page Number:
5 nfll.d.
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 32 Summacy of References Used Throughout Other Procedures of the ODCM 3.2.1 BVPS-1 and 2 UFSAR:
3.2.1.1 3.2.1.2 3.2.1.3 3.2.1.4 BVPS-1 UFSAR Section 11.2.3; Gaseous Waste Disposal System BVPS-1 UFSAR Section 11.2.4; Liquid Waste Disposal System BVPS-2 UFSAR Section 11.2; Liquid Waste Management Systems BVPS-2 UFSAR Section 11.3; Gaseous Waste Management Systems 3.2.2 Condition Reports and SAP Orders:
3.2.2.1 3.2.2.2 3.2.2.3 3.2.2.4 3.2.2.5 3.2.2.6 3.2.2.7 CR 971578, MEMBERS OF TIIE 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.
CR 980129, ODCM Procedure Matrix Discrepancies. CA-01, Revise Appendix F of the ODCM to correct discrepancies with 1/2-0M LS Surveillance Logs.
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.
CR 981488, Chemistry Related ODCM Procedures and ODCM Appendix F References. CA-01, Revise ODCM Appendix F to add Chemistry procedure references.
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.
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 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.
Beaver Valley Power Station
Title:
Procedure Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Pago Number.
6 nf 114 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 Surveillances of Unit 1 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 CR 02-05533, Procedure l/2-0DC-3.03, ATTACHMENT E Missing Information.
CA-01, Revise ODCM procedure l/2-ODC-3.03 {Table 3.3-12) to include minimum channels operable and associated actions when Flow Rate Measurement Device [FR-lLW-103] is inoperable.
3.2.2.13 CR 02-05711, TS and ODCM changes not reflected in 1OM-54.3.L5 Surveillance Log. CA-01, Revise l/2-ODC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes.
3.2.2.14 CR 02-06174, Tracking of Activities for Unit 1 RCS Zinc Addition Implementation. CA-13, Revise ODCM procedure l/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 1.1-1 a and 1 b) to include the addition of Zn-65 to ODCM liquid source term.
3.2.2.15 CR 03-02466, RF A-Radiation Protection Effluent Control Provide Recommendation on Processing when Performing Weekly Sample of
[1LW-TK.-7A/7B]. CA-02, Revise ODCM Procedure l/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit 1 and Unit 2.
3.2.2.16 CR 03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit 1 Containment Vacuum Pump Source-Term in ODCM procedure l/2-0DC-2.02, Attachment A, Table 2.1-la.
3.2.2.17 CR 03-06123, Enhance Table 3.3-6 of l/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 2nd PMM when the Unit 1 Mid or High Range Noble Gas Effluent Monitors are Inoperable.
3.2.2.18 CR 03-06281, Gaseous Tritium Sampling Required by ODCM (l/2-0DC-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
Title:
ProccduRi Number:
l/2-0DC-1.01 Unit:
1/2 Level OfUac:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Page Number:
7 of 114 7
3.2.2.19 CR 03-07487, Results ofNQA 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 1/2-0DC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.
3.2.2.20 CR 03-07668, 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 am01mt of Effluent Samples obtained during a power transient 3.2.2.21 CR 03-09288, LAR lA-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 CR 03-09959, RFA-Rad Protection Provide Clanfication to ODCM 1/Day Air Tritium Sample. CA-01, Revise ODCM procedure l/2-ODC-3.03 Attachment K
{Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere.
3.2.2.23 CR 03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure l/2-0DC-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 CR 04-00149, 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 CR 04-01643, Procedure Correction-Typographical Error in the ODCM. CA-01, Revise ODCM procedure l/2-0DC-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-lGW-13] to [PI-lGW-135].
3.2.2.26 CR 04-02275, Discrepancies in Table 3.3-13 of the ODCM. CA-01, Revise ODCM procedure l/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 CR 04-09895, Missed ODCM Channel Fw;ictional Test (Gas Effluent Sampler Flowrate). CA-04, Revise ODCM procedure l/2-ODC-1.01, Attachment C, Table F:3a to show that the Channel Functional Test requirements for the Unit 1 Sampler Flowrate Measuring Devices delineated in ODCM procedure l/2-0DC-3.03, Attachment F, Table 4.3-13 are being met by Form 1/2-ENV-01.04.F0l instead of lMSP-43.71-1
Beaver Valley Power Station
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Procedure Number.
l/2-0DC-1.01 Unit
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General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revmon:
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R nf 114 3.2.2.28 CR 05-01169, Chemistry Action Plan For Transition ofRETS, REMP and ODCM, CA-14 tbru CA-21, Revise ODCM procedures to change document owner from
Manager, Radiation Protection" to Manager Nuclear Environmental &
Chemistry.
3.22.29 CR 05-01390, Include GPS data in 2004 REMP Report and related 1/2-0DC and 1/2-ENV procedures. CA-02, revise ODCM procedure l/2-0DC-2.03 to include an update ofREMP sample locations (using the GPS Satellite data).
3.22.30 CR 05-03306, Incorporated Improved Technical Specifications (ITS). This includes transfer of programmatic controls for BV-2 Noble Gas Effluent Steam Monitors [2MSS-RQ101A], [2MSS-RQ101B] and [2MSS-RQ101C] from the Technical Specifications to ODCM procedure l/2-0DC-3.03 (Attachment D Tables 3.3-6 and 4.3-3). This was permitted via Unit 1/2 Technical Specification Amendments No. 278/161.
3.22.31 CR 05-03854, ODCM Figure for Liquid Effluent Release Points Needs Updated.
CA-01, revise ODCM procedure l/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.
3.2.2.32 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure l/2-ODC-2.01 to update the alarm setpoints of[RM-lRM-100]
and [RM-lDA-100] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275. Also, CA-04; revised ODCM procedure l/2-0DC-2.02 to add a":s designation to all alarm setpoints for Unit 1 and Unit 2 low range noble gas effluent monitors.
3.2.2.33 CR 06-6476, Procedure l/2-0DC-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.
3.2.2.34 SAP Order 200197646-0110: Revise ODCM procedure 1/2ODC-3.03, l/2-HPP-3.06.001, 1/2-ENV-05-01, Form 1/2-HPP-3.06.001.F05 and Form l/2-ENV-05.1.F0S to incorporate revised outside liquid storage tank activity limits via Calculation Package No. ERS-ATL-95-007, R2.
3.2.2.35 SAP Order 200240681: Revise ODCM procedure l/2-ODC-3.03 (Attachment E Table 3.3-12) to add an alternate Action when the primary Flow Rate Measurement Device [FT-ICW-101-1] is not OPERABLE. The alternate Action (25A) uses local measmements (as described in IMSP-31.06-n to determine a total dilution flow rate during liquid effluent releases.
3.2.2.36 CR 06-04944: ODCM 3.03 Attachment E conflict between Applicability and Action Statement CA-01; revise ODCM procedure l/2-ODC-3.03, Attachment E to clarify Applicability for tank level indicating devices is during addition to the tank.
Beaver Valley Power Station
Title:
Proccdurc Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
?.Q Page Number:
Q nf 114 3.2.2.37 CR 07-12924 and SAP Order 200247228-0410: Revise ODCM procedure l/2-0DC-3.03 (Attachment F Tables 3.3-13 and 4.3-13) to clarify the Functional Location of the Sampler Flow Rate Monitors for the BV-2 gaseous effluent release pathways. Specifically, the procedure was changed to refer to Functional Location
[2HVS-FIT101-1] instead of [2HVS-FIT101], [2RMQ-FIT301-1] instead of
[2RMQ-FIT301], [2HVL-ffil 12-1] instead of [2HVL-ffil 12], and
[2RMQ-FIT303-1] instead of [2RMQ-FIT303].
3.2.2.38 CR 09-53803-10: Revise ODCM procedure l/2-0DC-3.03 to add EAL related area and process monitors to Attachment D Tables 3.3-6 and 4.3-3 3.2.2.39 CR 09-53803-13: Revise ODCM procedure l/2-0DC-1.01 to add appropriate MSP and OST references for EAL related area and process monitors to the procedure matrix.
3.2.2.40 SAP Order 200257692-0360 and 0390: Revise the procedure matrix of l/2-0DC-1.01 to remove obsolete forms and procedures used for ODCM Channel Checks. Specifically, Form 1/2-ADM-0606.F0l, Form 1/2-ADM-0606.F02, Form 1/2-HPP-3.07.003.F0l and procedures 1/2-HPP-3.06.005, l/2-HPP-3.06.006 and 1/2-HPP-3.06.012 were removed from the Attachment C Tables of the procedure matrix.
3.2.2.41 SAP Order 200197646-0300 and CR 07-31083: Revise ODCM procedure l/2-0DC-3.03 to add a definition for Channel Functional Test, and revise the definition for Channel Operational Test to indicate that these definitions have the same requirements and, therefore, are considered equal.
3.2.2.42 SAP Order 200247228-0450: Revise l/2-0DC-3.03 Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added 61arifications, as follows: (1) add the word "or" where it is missing from Attachment F, Table 3.3-13 and 4.3-13, (2) remove grab samples from the list of alternates in Table 3.3-13 and 4.3-13, because a grab sample is an "action", not an "alternate",
(3) add notations in Table 3.3-12 and 3.3-13 to indicate that Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action band 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days, and (4) remove surveillances for Preplanned Method of Monitoring (PMM) from Table 4.3-3, because surveillances only apply to instruments, not methods.
3.2.2.43 SAP Order 200240681-0020 and 0040: Revise l/2-0DC-3.03 Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1st and 2nd alternates to the flow rate measurement devices used for the cooling tower blowdown line.
Beaver Valley Power Station
Title:
Procedure Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Page Number:
10 nf 114 3.2.2.44 CR 05-00004-15, CR 05-00004-17 and SAP Order 200197646-0010 to revise
.l/2-ODC-2.01. Add the Coolant Recovery Tanks [1BR-TK-4A/4B] as Liquid Waste Tanks to Section 8.4 description and Attachment D Figures 1.4-1 and 1.4-2.
Add a default 2-tank volume recirculation time of 45.7 hrs for the Coolant Recovery Tanks [1BR-TK-4A/4B] to Attachment B Table 1.2-la. Add the Cesium Removal Ion Exchangers [lBR-I-lA/lB and 2BRS-IOE21A/21B] to Section 8.4 description and Attachment B Figures 1.4-1 and 1.4-2. Revise the recirculation times in Attachment B Table 1.2-1 a and 1.2-1 b to indicate the times for nominal tank volume and maximum tank volume.
3.2.2.45 SAP Order 200197646-0660. Revise l/2-ODC-2.01 Attachment D Figure 1.4-3 to remove STP Outfalls 113 and 203 due to retirement of the Sewage Treatment Plants and to remove Outfall 501. Water is no longer discharged via these outfalls.
3.2.2.46 SAP Order 200197646-0810. Revise l/2-ODC-2.01 to incorporate alarm setpoints for all possible detector combinations for [RM-lDA-100]. Specifically, due to obsolescence of the original Model 843-30 and 843-32 detectors that were previously installed in [RM-lDA-100], the vendor has upgraded them to Model 843-30R and 843-32R detectors, which include upgraded efficiency data as well.
3.2.2.47 CR 10-77489, Procedure l/2-0DC-2.03 needs revised for labeling discrepancies.
Corrected sampling location descriptions for REMP TLD #94 and #95; Changed sample designation from #49 to #49A; Clarified program requirements for garden sampling.
3.2.2.48 CR 10-86844 revises l/2-0DC-2.01 to remove description that batch releases of liquid waste are processed by recirculation through eductors. Deleted Attachment B which referenced minimum liquid waste batch release recirculation times and added description that liquid waste recirculation times to achieve two tank volumes are calculated based upon actual tank volume and pump capacity.
3.2.2.49 CR 10-85877, Selenium-75 (Se-75) discharge via Ul/U2 Process Vent CA-02 revises ODCM procedure l/2-0DC-2.02 to include dose factors for Se-75 (documented in RFCA Packages# BV20100284, BV20100285, and BV20110013).
3.2.2.50 CA G203-2011-97516-001, Retire TLD Station #88 and add Station #88A.
3.2.2.51 CR G203-2011-02332, Inability to meet ODCM requirements for RillvfP milk sampling in 2011 and CA G203-2011-02332-1, Make changes to the ODCM.
3.2.2.52 CR 2012-02583 and ECP 11-0049 implement changes to the design of the liquid waste system for Phase 2 of Coolant Recovery Project 3.2.2.53 SAP Notification 600747531, Update l/2-ODC-2.01 for RM-lRW-100.
3.2.2.54 CR-2012-05875, Antimony-126 identified in the liquid waste system.
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29 11 of 114 3.2.2.55 SAP Notification 600765150, Request from Operations to allow discharge of water in high level drains tanks [L W-TK-2A/B] through low level waste tanks
[LW-TK.-3A/B] viaRM-LW-104.
3.2.2.56 CA 2012-15547-7, To address the extent of condition with potential gaps in Radiological Effluent Program, evaluate the need to place appropriate ODCM controls on various non-radiological tanks and sumps throughout the site.
3.2.2.57 CR-2016-10379, 2014 and 2015 REMP Report Issues: Revisions to REMP location maps 3.2.2.58 SAP Notification 601054826: Revise reference on 1/2-HPP-4.02.009.F0l 3.2.2.59 SAP Notification 601018638: 2016 REMP/RETS Tracking For ARERR/AREOR; task 10, Site 2.1, ATI Allegheny Ludlum-Closed 3.2.2.60 CR-2017-04211, Lack of isokinetic sampling for ODCM requirements 3.2.2.61 CR-2018-02456, Rad Effluents Inspection Preliminary Licensee Identified Green Non-cited Violation 3.2.3 Calculation Packages:
3.2.3.1 ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for 1/2-ENV-05.06 3.2.3.2 ERS-SFL-85-031; 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-lffiM-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 ofODCM 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-RQ112 3.2.3.8 ERS-ATL-95-006; Re-evaluation ofTS/ODCM SR's 4.11.1.1.3, 4.11.1.1.4 and Notes e and g ofTS/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)
Beaver Valley Power Station Yrtle:
Procedure Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Rcviaion:
?Q Pago Number:
1? nf 114 3.2.3.11 Vendor Calculation Package No. 8700-UR(B)-223; Impact of Atmospheric Containment Conve!§ion, 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) 3.2.3.15 ERS-MPD-93-007; BVPS-1 Gaseous Radioactivity Monitor Emergency Action Levels 3.2.3.16 ERS-ATL-93-021; Process Alarm Setpoints for Liquid Effluent Monitors 3.2.3.17 ERS-LMR-12-001; ODCM P and R Values for Carbon-14 3.2.3.18 Engineering Change Package No. ECP-12-0478; Liquid Waste Demin Project:
Installation of new Demineralizers in Solid Waste Building 3.2.3.19 Engineering Change Package No. ECP-16-0026; Pump/Motor Assembly Replacement 3.2.3.20 ERS-LMR-15-006; Additional Effluent Dose Factors 3.2.3.21 Engineering Change Package No. 17-0378: Retirement of Radiation Monitors at Beaver Valley Unit #1 3.2.3.22 Engineering Change Package No. ECP-16-0113; BVl Process Radiation Monitoring System Replacement 3.2.3.23 Engineering Change Package No. ECP-13-0829: Install Blank-Off Flanges on the Inlet and Outlet of Unit 2 Condensate Polishing System 3.2.3.24 Engineering Change Package No. ECP-19-0230: Remove Effluent Flow Path to the River and Abandon Radiation Monitor RM-lDA-100 3.2.4 Internal Letters:
3.2.4.1 3.2.4.2 3.2.4.3 DLC Response to NRC Unresolved Item 50-334/83-30-05, Radiation Monitor Study-Particle Distribution Evaluation, November 26, 1986.
NDlSHP:776, BVPS-1 ODCM Table 2.2-2, Appendix B, February 12, 1988 ND3NSM:3431; Technical Specification Verification Effort, August 11, 1988
)
Beaver Valley Power Station
Title:
Procedure Number.
l/2-0DC-1.01 Unit 1/2 Level OfUae:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
?Q Page Number.
13 of 114 3.2.4.4 3.2.4.5 3.2.4.6 3.2.4.7 3.2.4.8 3.2.4.9 NDLNSM:3522; Technical Specification Verification Effort Checklist, September 14, 1988 NDlNSM:3652; Technical Specification Verification Effort, November 21, 1988 NPD3SHP:2466; Self-Assessment of the Liquid and Gaseous Effluent Processes at BVPS - Final Report, July 16, 1997 NPD3SHP:2257; ODCM Liquid Waste Recirculation Rates, February 11, 1998 NPD3SHP:2643; Action 28 ofODCM Appendix C Table 3.3-13, January 14, 1999 ND3MNO:4309; Response to Request for Technical Specification Interpretation, April 20, 1999.
I 3.2.5 Contractor Technical Evaluation Reports:
3.2.5.1 3.2.5.2 3.2.5.3 3.2.5.4 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 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 NUS-2173; Development of Terrain Adjustment Factors For Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Dispersion Model, June 1978 UCRL-50564; Concentration Factors of Chemical Elements in Edible Aquatic Organisms, Revision 1, 1972 3.2.6 NRC Letters:
3.2.6.1 3.2.6.2 3.2.6.3 3.2.6.4 3.2.6.5 Unit 1 Technical Specification Amendment 66, March 28, 1983 Beaver Valley Unit 2 - Offsite Dose Calculation Manual, ODCM (TAC 63996),
July 14, 1987 Beaver Valley Units 1 and 2 - Acceptance of the Offsite Dose Calculation Manuals
{TAC 93996 and 67421), March 2, 1989 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-188/2A-70 (LAR 1A-175/2A-37), Implemented August 7, 1995 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-194/2A-77 (LAR's 1A-231/2A-101), Implemented December 1, 1995
Beaver Valley Power Station
Title:
Proccdurc Number:
1/2-0DC-l.0l Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes R.evisioo:
29 Pago Number:
1..i nf 114 3.2.6.6 3.2.6.7 3.2.6.8 3.2.6.9 Unit 1/2 Technical Specification Figure 5.1-2, including Amendments 1A-202/2A-83 (LAR 1A-234/2A-107, Implemented June 9, 1997 Unit 1/2 Technical Specifications 6.9.1.10 and 6.9.2, including Amendments 1A-220/2A-97 (LAR 1A-246/2A-116), Implemented May 20, 1999 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 1A-246/2A-124 (LAR 1A-287/2A-159), Implemented April 11, 2002 I
Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5, 6.8.6, and 6.9.2 including Amendments 1A-250/2A-130 (LAR 1A-291/2A-163), Implemented August 7, 2002
3.2.7 NUREG's
3.2.7.1 3.2.7.2 3.2.7.3 3.2.7.4 3.2.7.5 3.2.7.6 3.2.7.7 3.2.7.8 3.2.7.9 NUREG-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors, (PWR-Gale Code), Revision 1, April 1985 NUREG 0133; Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants, October 1978 NUREG-0172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, November 1977 NUREG-0324; XOQDOQ, Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations, September 1977 NUREG-0472; Radiological Effluent Technical Specifications for PWR's.
NUREG-0800, Standard Review Plan, Postulated Radioactive Releases Due to Liquid-Containing Tank Failures, July 1981 NUREG-1301; Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1), April 1991 NUREG-1431; Standard Technical Specification - Westinghouse Plants Specifications NUREG/CR-2919; Meteorological Evaluation of Routine Effluent Releases At Nuclear Power Stations, September 1982
Beaver Valley Power Station
Title:
Proccdurc NIIIllher:
l/2-0DC-1.01 Unit 1/2 Level OfUac:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Page Number.
15 of 114 3.2.8 Regulatory Guides:
3.2.8.1 3.2.8.2 3.2.8.3 3.2.8.4 RG-1.23; Meteorological Measurement Program For Nuclear Power Plants 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 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 RG-1.113; 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 l/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.
3.3.10 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.
Beaver Valley Power Station Trtlc:
ODCM: Index, Matrix and History of ODCM Changes 4.0 RECORDS AND FORMS 4.1 Records Procedure Number:
l/2-ODC-1.01 Unit 1/2 Level Of Use:
General Skill Reference Page Number:
16 nf 114 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.
4.1.2 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 program 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 1 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, (3.2I) 10 CFR 50.36a, (3.2.2) Appendix I of 10 CFR Part 50,(3.23) and 40 CFR Part 190_(3.24) 5.2 This ODCM is based on the NUREG's and Generic Letter documents from the United States Nuclear Regulatory Commission. (3.1.1, 3.1.2, 3.13, 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.t.5) 5.3 The ODCM has been prepared as generically as possible in order to minimiz.e 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.
5.3.1 An implementation procechrre for control of the ODCM is included in l/2-ADM-1640.<3*1.6) 5.4 This procedure also contains information that was previously contained in Appendix F of the previous BV-1 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".
Beaver Valley Power Station
Title:
Proccdnre Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
?()
Pago Numbor:
17of114 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 CPR 20.1302, 40 CFR Part 190, 10 CPR 50.36a, 10 CPR 72.104 and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of eflluent 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.t.6) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001 (3.t.s) and l/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 l/2-0DC-1.01, ODCM: Index, Matrix and History ofODCM changes (formerly: ODCM Index and Appendix F) 8.1.1.1 8.1.1.2 8.1.1.3 8.1.1.4 8.1.1.5 History of ODCM Changes Summary of ODCM References List of Tables (ATTACHMENT A)
List of Figures (ATTACHMENT B)
Matrix of Procedures Used to Meet ODCM Controls (ATTACHMENT C) 8.1.1.5.1 8.1.1.5.2 8.1.1.5.3 8.1.1.5.4 8.1.1.5.5 8.1.1.5.6 8.1.1.5.7 BV-1 Radiation Monitor Surveillances BV-1 Liquid Effluent Monitor Surveillances BV-2 Liquid Effluent Monitor Surveillances BV-1 Gaseous Effluent Monitor Surveillances BV-2 Gaseous Effluent Monitor Surveillances BV-1 and 2 Liquid Effluent Concentration Surveillances BV-1 and 2 Liquid Effluent Dose Surveillances
,f Beaver Valley Power Station Procedure Nnmber.
ii l/2-0DC-1.01
Title:
Unit Level Of Uae:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes R.cviitlon:
Page Number:
?Q 1 R of 114 8.1.1.5.8 BV -1 and 2 Liquid Effluent Treatment Surveillances 8.1.1.5.9 BV-1 and 2 Gaseous Effluent Air Dose Surveillances 8.1.1.5.10 BV-1 and 2 Gaseous Effluent Particulate and Iodine Surveillances 8.1.1.5.11 BV -1 and 2 Gaseous Effluent Treatment Surveillances 8.1.1.5.12 BV-1 and 2 Gaseous Effluent Total Dose Surveillances 8.1.1.5.13 BV-1 and 2 Gaseous Effluent REMP Surveillances 8.1.1.5.14 BV-1 and 2 Gaseous Effluent Land Use Census Surveillances 8.1.1.5.15 BV-1 and 2 Gaseous Effluent Interlaboratory Comparison Program Surveillances 8.1.2 l/2-ODC-2.01, ODCM: Liauid Effluents (formerly; ODCM Sections 1 and 5) 8.1.2.l Alarm Setpoints 8.1.2.1.1 BV-1 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-1 Liquid Radwaste Treatment System Components 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
Beaver Valley Power Station
Title:
Proccdurc Number:
l/2-0DC-1.01 Unit 1/2 Level OfUac:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
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19 nf114 8.1.2.5 Site Boundary for Liquid Effluents 8.1.2.5.l Liquid Effluent Site Boundary 8.1.3 l/2-ODC-2.02, ODCM: Gaseous Effluents (formerly; ODCM Sections 2 and 5) 8.1.3.1 8.1.3.2 8.1.3.3 8.1.3.4 8.1.3.5 Alarm Setpoints 8.1.3.1.1 8.1.3.1.2 8.1.3.1.3 8.1.3.1.4 8.1.3.1.5 8.1.3.1.6 BV-1 Setpoint Determination Based On A Calculated Mix BV-1 Setpoint Determination Based On Analysis Prior To Release BV-2 Setpoint Determination Based On A Calculated Mix BV-2 Setpoint Determination Based On Analysis Prior To Release BV-1/2 Setpoint Determination Based On A Calculated Mix BV-1/2 Setpoint Determination Based On Analysis Prior To Release Compliance With 10 CFR 20 Dose Rate Limits 8.1.3.2.1 8.1.3.2.2 Dose Rate Due To Noble Gases Dose Rate Due To Radioiodines And Particulates Compliance With 10 CFR 50 Dose Limits 8.1.3.3.1 8.1.3.3.2 Doses Due To Noble Gases Doses Due To Radioiodines And Particulates Gaseous Radwaste Treatment System 8.1.3.4.1 8.1.3.4.2 BV-1 Gaseous Radwaste Treatment System Components BV-2 Gaseous Radwaste Treatment System Components Site Boundary for Gaseous Effluents 8.1.4 l/2-0DC-2.03, ODCM: Radiological Environmental Monitoring Program (formerly; ODCM Section 3) 8.1.4.1 Program Requirements
Beaver Valley Power Station Trtle:
Procedure Number:
1/2-0DC-1.0l Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Page Number:
?n of 114 8.1.5 l/2-0DC-2.04. ODCM: Information Related to 40 CFR 190 (formerly; ODCM Section 4) 8.1.5.l 8.1.5.2 8.1.5.3 Compliance with 40 CPR 190 Dose Limits Report Requirements Inside the Site Bmmdary Radiation Doses 8.1.5.3.l Gaseous Effluent Site Boundary 8.1.6 l/2-0DC-3.01. ODCM: Dispersion Calculational Procedure and Source Tenn Inputs (formerly; ODCM Appendix A & B) 8.1.6.1 8.1.6.2 8.1.6.3 8.1.6.4 8.1.6.5 8.1.6.6 Dispersion and Deposition Parameters BV-1 and 2 Release Conditions BV-1 Liquid Source Tenn Inputs BV-2 Liquid Source Tenn Inputs BV-1 Gaseous Source Tenn Inputs BV-2 Gaseous Source Tenn Inputs 8.1.7 l/2-0DC-3.02. ODCM: Bases for ODCM Controls (formerly; ODCM Appendix D)
I 8.1.7.1 Bases 3.3.3.1: Radiation Monitoring Instrumentation 8.1. 7.2 Bases 3.3.3.9: Radioactive Liquid Eflluent 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 Eflluent Concentration 8.1. 7.5 Bases 3.11.1.2: Liquid Eflluent 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 Eflluent 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
Beaver Valley Power Station
Title:
Procedure Number:
l/2-0DC-1.01 Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Page Number:
21 of114 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 l/2-0DC-3.03. ODCM: Controls for RETS and REMP Programs (formerly; ODCM Appendix C) 8.1.8.1 8.1.8.2 8.1.8.3 8.1.8.4 8.1.8.5 8.1.8.6 8.1.8.7 8.1.8.8 8.1.8.9 8.1.8.10 8.1.8.11 8.1.8.12 8.1.8.13 8.1.8.14 8.1.8.15 8.1-:8.16 8.1.8.17 Controls 3.0.1 thru 3.0.4: Applicability Controls 4.0.1 thru 4.0.4: Surveillance Requirements Control 3.3.3.1: Radiation Monitoring Instrumentation Control 3.3.3.9: Radioactive Liquid Effluent Monitoring Instrumentation Control 3.3.3.10: Radioactive Gaseous Monitoring Instrumentation, Control 3.11.1.1: Liquid Effluent Concentration Control 3.11.1.2: Liquid Effluent Dose Control 3.11.1.3: Liquid Radwaste Treatment System Control 3.11.1.4: Liquid Holdup Tanks Control 3.11.2.1: Gaseous Effluent Dose Rate Control 3.11.2.2: Dose-Noble Gases Control 3.11.2.3: Dose - Radioiodines, Radioactive Material in Particulate ~ orm, and Radionuclides Other Than Noble Gases Control 3.11.2.4: Gaseous Radwaste Treatment System Control 3.11.2.5: Gas Storage Tanks Control 3.11.4.1: Total Dose Control 3.12.1: REMP Program Requirements Control 3.12.2: REMP -Land Use Census
Beaver Valley Power Station Trtle:
Procedure Number:
l/2-0DC-1.01 Level OfUae:
Unit:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revwon:
')Q Page Number:
n of 114 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) ofBV-1 ODCM {Issue 1), Effective January, 1984 821.1 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 :MmdJ.28, 1983.
8.2.2 Change {2) ofBV-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 8.2.2.1.2 8.2.2.1.3 8.2.2.1.4 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.
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. Tue equations were revised to clarify flow rate terminology.
Section 2.0: Section 2.2.2 was revised to delete the food and ground pathways for gaseous dose rate calculations of I-131, tritium, and radionuclides in particulate form with half lives greater than 8 days.
Section 2.0: Table 2.2-13 was revised to include 7 organs rather than only the maximum organ. Also, the receptor was changed from infant to child, and addition/deletion ofnuclides to be consistent with the Technical Specifications and nuclides identified at BV-1.
8.2.3 Change {3) ofBV-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.
Beaver Valley Power Station Trtle:
Procedure Nmnbcr:
l/2-0DC-1.01 Unit 1/2 Level OfUsc:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revia:lon:
2Q Page Number:
?~ n-f 11.:1 82.3.1.2 8.2.3.1.3 Section 1.0 and 2.0: Revise the 31-day dose projection limits and methodology in Sections 1.3.2, 2.3.12, 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.
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 SPINO 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) ofBV-1 ODCM (Issue 2), and BV-2 ODCM (Issue 1, Rev 1), Effective July, 1987 8.2.4.1 With the start-up ofBV-2 in the second half of 1987, the BV-1 ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows:
8.2.4.1.1 8.2.4.1.2 8.2.4.1.3 8.2.4.1.4 8.2.4.1.5 Produce functionally compatible BV-1 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 1 (historical) and operation ofBV-2 began with Issue 1, Revision 1 of the BV-2 ODCM.
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.
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.
Section 2.0: Separate ground level gaseous releases were maintained.
The BV-1 ODCM was updated to incorporate the BV-2 five year meteorology base. Gaseous source terms were revised to that calculated for BV-1 in the BV-2 FSAR, and terms were added for calculation of a turbine building release.
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.
Beaver Valley Power Station Trtle:
Procedure Number.
l/2-0DC-1.01 Unit:
1/2 Level OfUac:
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?.4 of 114 8.2.4.1.6 Section 2.0: Formal justification was provided for use of the "T" factor as descnbed 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).
8.2.5 Change {5) ofBV-1 ODCM {Issue 2, Rev 1}, and BV-2 ODCM {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} ofBV-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 8.2.6.1.2 8.2.6.1.3 8.2.6.1.4 8.2.6.1.5 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)
Section 1.0: Corrected typos to BV-1 ODCM Equation 1.1-8 to show differentiation between the two f s, and add the division sign. (See Justification 1)
Section 1.0: Re-define Fk in equation 1.3-1 of both ODCMs, as allowed by the NRC. (See Justification 1)
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)
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-1 ODCM. (3)
Correct typos in Table 3.0-1 of both ODCMs. (4) Coqect typos in Figure 3.0-3 of both ODCMs.
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?<1:i nf 114 8.2.6.2 8.2.6.1.6 8.2.6.1.7 8.2.6.1.8 8.2.6.1.9 8.2.6.1.10 8.2.6.1.11 8.2.6.1.12 Section 2.0: Add a Reference to Section 2 of the BV-1 ODCM. (See Justification 3)
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)
Section 2.0: Revise BV-1 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)
Section 2.0: Provide re-verified Prr values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1)
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)
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)
Appendix B: Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3)
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-1 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 ODCM/NUREG-0133 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.
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?r. nf 114 8.2.6.2.2 8.2.6.2.3 As requested by DLC letters ND3NSM:3431, NDINSM: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.
As delineated in letter NDlSHP: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 I.
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 setpoip.t.
Therefore, this change does not adversely impact the accuracy or reliability of setpoint calculations.
8.2.7 Change (7) ofBV-1 and 2 ODCM (Issue 3), Effective August, 1995 8.2.7.1 The combined ODCM contains the following changes:
8.2.7.1.1 8.2.7.1.2 Prior to ISSUE 3, BV-1 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.
Section 1.0: Revised Section 1.0 (Liquid Effluents) to show compliance with 10 CFR 20 Appendix B (20.1001 - 20.2401), Table 2, Col. 2 EC's. This includes the following: (1) Revising the alarm setpoints for monitors [RM-ILW-104, RM-lLW-116, and 2SGC-RQ100]. (2) Updating the BV-1 monitor detection efficiencies. (3)
Updating discharge rate and dilution rate parameters for BV-1 and BV-
- 2. (4) Adding the alarm setpoints for monitors [RM-IRW-100, RM-IDA-100, 2SWS-RQ101, and 2SWS-RQ102].
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27 nfl 14 8.2.7.1.3 8.2.7.1.4 8.2.7.1.5 8.2.7.1.6 8.2.7.1.7 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-1 or BV-2, then an a orb 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 1.1-lb 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-1 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-1 and BV-2 respectively. A cross reference for ODCM equations is l)l'Ovided in the Table Of Contents.
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).
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).
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 dispersion parameters are now included in one area of the ODCM.
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. 1 (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 descnbed in the Technical Specification.
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?~ nf 114 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.
8.2.7.1.9 Appendix E: This is a new Appendix to the ODCM. The Annual Radioactive Eflluent Release Report and the Annual Radiological Environmental Report reporting requirements are listed in this appendix totheODCM.
8.2.7.1.10 There are three differences (i.e., non-editorial changes) in this ODCM revision when compared to the previous BV-1 and BV-2 Technical Specifications. These are the only changes that are identified by revision bars. These differences are as follows:
8.2.7.1.10.1.1 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-1 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 8.2.7.1.10.2 10 CPR 20.1302, 40 CPR Part 190, 10 CFR 50.36a, and Appendix I to 10 CPR 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.
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
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?Q nf 114 8.2.7.1.10.3 the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous eflluents 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 eflluent 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 eflluent, 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 UNRES1RICTED 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 1 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 Eflluent 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 limiting radioactivity concentrations in eflluents, 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 eflluents 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)
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10 nf 11.:1 8.2.7.2 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 1 (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 eflluents, 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 eflluent 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 eflluent 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 eflluents 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,orsetpointcalculations.
In summary, Per Generic Letter 89-01, the transfer ofRETS procedural details fulfi11s 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.
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11 of 114 8.2.8 Change (8) ofBV-1 and 2 ODCM (Issue 3, Rev 1), Effective October, 1995 8.2.8.1 8.2.8.2 A description of the changes implemented with this revision are as follows:
8.2.8.1.l 8.2.8.1.2 8.2.8.1.3 8.2.8.1.4 8.2.8.1.5 8.2.8.1.6 8.2.8.1.7 8.2.8.1.8 Index: Editorial changes were made for clarity. (See justification 1)
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)
Appendix A: A change was made to Table 1.1 so that the letter A would proceed the table number. (See justification 1)
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)
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-RQ112] from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the three gaseous efiluent 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).
Appendix D: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)
Appendix E: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)
Appendix F: This is a new Appendix to the ODCM. It contains plant procedure references for Radiological Eftluent Technical Specification (RETS) that were transferred from the Technical Specification Procedure Matrix. (See justification 1)
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 eftluent control required by 10 CPR 20.1302, 40 CPR 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 eftluent dose or setpoint calculation.
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32 of 114 8.2.8.2.2 8.2.8.2.3 This change resulted from revising the bioaccumulation factor (BF) for niobium from the value posted in Table A-1 of Regulatory Guide 1.109, Revision 1, 1977 (30,000 pCi/kg per pCi/1). Since this change in niobium BF ( as documented and justified in Appendix A to Calculation Package No. ERS-AlL-83-027) merely removes the conservatism associated with organism uptake, then the change will maintain the level of radioactive eftluent control required by 10 CFR 20.1302, 4-0 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.
This change removes the process flow rate operability and surveillance requirements for BV -2 Gaseous Eftluent Radiation Monitors
[2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ112] 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-AlL-90-021.
A safety analysis and a no significant haz.a.rds 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 ofTSCR No. 1A-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-1 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 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
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'H nfl 14 8.2.8.2.4 8.2.8.2.5 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.
This change adds alternate system eflluent flowrate measuring devices for the three BV-1 gaseous eflluent 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 eflluent 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 eflluent dose or setpoint calculations.
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-AlL 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 eflluent 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 than any evaluated previously. (3) There is no reduction in the margin of safety.
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14 nf 114 8.2.9 Change (9) ofBV-1 and 2 ODCM (Issue 3. Rev 2). Effective May 1997 8.2.9.1 8.2.92 A description of the changes implemented with this revision are as follows:
8.2.9.1.1 8.2.9.1.2 8.2.9.1.3 8.2.9.1.4 8.2.9.1.5 8.2.9.1.6 Index: Editorial changes were made for clarity. (See Justification 1)
Section 1.0: Clarifying statements were added to Tables 1.2-la and 1.2-1 b 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)
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)
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).
Appendix E: Corrected typographical error on Table 6.9-1. (See Justification 1)
Appendix F: Added procedure details to Tables 11, 12 and 13. (See Justification 1)
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 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a and Appendix I to 10 CPR 50. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
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~" of 114 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-1 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-1 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) ofBV-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) ofBV-1 and 2 ODCM (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 8.2.11.1.2 Index: Editorial changes were made for clarity.
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 I Containment Building. The actual sample locations and descriptions remain unchanged. Also, the 4 individual quadrant maps showing TI,D locations were consolidated into 1 map. This is a Corrective Action to Condition Report CR 980353.
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~,;; ofl 14 8.2.11.1.3 8.2.11.1.4 8.2.11.1.5 8.2.11.1.6 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.
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-1GW-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-lVS-109 Channel 5] was added as an alternate to [RM-1VS-101B] and [RM-lVlS-110 Channel 5] was added as an alternate to [RM-1VS-107B]. [RM-lGW-109 Channel 5] was not added as an alternate to [RM-1GW-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-lVS-109 Channel 1] was added as an alternate to [RM-lVS-lOlA], [RM-lVS-1110 Channel 1] was added as an alternate to [RM-VS-1107A], and [RM-lGW-109 Channel 1] was added as an alternate to RM-1GW-108A.
Appendix E: Corrected typographical errors on Table E:6.9-1 Appendix F: Updated the procedure details for primary and alternate instrumentation included in Appendix C Tables 3.3-13 and 4.3-13.
Reduced the 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.
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~7 nf 114 8.2.12 Change (12) ofBV-1 and 2 ODCM (Issue 3, Rev 5), Effective November 1998 8.2.12.l 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 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.
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1R of 114 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 iB involved by adding an additional sample site and sample method. ThiB evaluation is based on the following: (1) There iB no increase in the probability or consequences of accidents or malfunctions of equipment important to safety. (2) There iB no creation of a possibility for an accident or malfunction of a different type than any evaluated previously. (3) There iB no reduction in the margin of safety.
8.2.13 Change (13) ofBV-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 8.2.13.1.2 8.2.13.1.3 Index: Editorial changes were made for clarity.
Section 3.0: Updated figure number and table reference. Removed a redundant upstream environmental surface water sampling location.
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 1 and Unit 2 instruments [FT-lCW-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 gas~us 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 6.9.2fto 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. ClarifiedControls3.12.1 and 3.12.2toensurecompliancewithNUREG-1301.
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1Q nf 114 8.2.13.1.4 Appendix E: Made editorial changes for clarity. Changed reference of Special Report compliance requirement from Technical Specification 6.9.2fto 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 1 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 impacttheaccuracyorreliabilityofeffluent doseorsetpoint calculations.
8.2.14 Change (14) ofBV-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:
K2.14.2.l 8.2.14.22 Index: Editorial changes were made for clarity. References to condition reports CR 982097, CR 992652 and CR 993021 were added.
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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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(l) for RM-lDA-100 (Corrective Action to Condition Report CR 993021). Add clarification to Table 3.3-13 and 4.3-13 to show the plant specific Mark Numbers for the primary and alternate BV-1 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 Eftluent 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
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40 nf 114 8.2.14.2.3 Action 29 and Action 32 are applicable for continuous releases. Added an alternate method in lieu of grab sample collection (i.e., 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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.
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 (i.e., HPM Appendix 1) when these logs are used satisfy ODCM Appendix C Surveillances and Actions (Corrective Action to Condition Report CR 992652).
8.2.14.3 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 10CFR50.59 applicability. In summary, the BVPS-1 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-1301 ). Therefore, these changes will maintain the level of radioactive effluent control required by 1 0CFR20. l 302, 40CFR Part 190, 10 CFR50.36a, and Appendix I to 10CFR50. Also, these changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations.
8.2.15 Change (15) ofBV-1 and2 ODCM {Rev 15), EffectiveAugust2000 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.
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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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> flow rate estimations (i.e.; 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.
8.2.15.2 The justification used for change (15) to the ODCM is as follows:
82.15.2.1 8.2.15.2.2 Some of these changes are considered editorial in nature. These changes were screened for 10CFR50.59 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 10CFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to 10CFRSO. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
The change to allow use of design (maximum) system flow rates in lieu of 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> flow rate estimations (for five of the eight gaseous eflluent release pathways) was screened for 10CFRS0.59 applicability and determined not to impact the BVPS-1 and 2 UFSAR's. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 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 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 oralarmsetpointcalculation.
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?Q 4?nf114 8.2.16 Change (16) ofBV-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 8.2.16.1.1.1 8.2.16.1.1.2 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 8.2.1611.1.8 8.2.16.1.2 The entire BV-1 and 2 ODCM was converted to the ODC format as delineated in l/2-ADM-0100. As part of this process, the ODCM was separated into eight procedures as follows:
l/2-ODC-1.01, Rev 0; ODCM: Index, Matrix and History of ODCM Changes (formerly; ODCM Index and Appendix F) l/2-ODC-2.01, Rev 0; ODCM: Liquid Effluents (formerly; ODCM Section 1 and 5) l/2-0DC-2.02, Rev 0; ODCM: Gaseous Effluents (formerly; ODCM Section 2 and 5) l/2-0DC-2.03, Rev 0; ODCM: Radiological Environmental Monitoring Program (formerly: ODCM Section 3) l/2-ODC-2.04, Rev 0; ODCM: Information Related to 40 CPR 190 (formerly; ODCM Section 4) l/2-ODC-3.01, Rev 0; ODCM: Dispersion Calculational Procedure and Source Term Inputs (formerly; ODCM Appendix A & B) l/2-0DC-3.02, Rev 0; ODCM: Bases for ODCM Controls (formerly; ODCM Appendix D) l/2-0DC-3.03, Rev 0; ODCM: Controls for RETS and REMP Programs (formerly; ODCM Appendix C and E)
Procedure l/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 1A-246/2A-124.<326*8>
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.d~ of 114 8.2.16.1.3 Procedure l/2-0DC-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.C32 -6*8> Specifically, this includes the Mid and High Range Channels of Noble Gas Eflluent Monitors [RM-lVS-109 (7 and 9), RM-lVS-110 (7 and 9), RM-lGW-109 (7 and 9), and 2HVS-RQ109C and 109D], the Atmospheric Steam Dump Valve/Code Safety Relief Valve Discharge Monitors [RM-lMS-l00A, Band CJ and Auxiliary Feedwater Pump Turbine Exhaust Monitor [RM-lMS-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 l/2-ODC-3.03, Rev 0: Added clarifications to ODCM Control 3.3.3.9 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.
8.2.16.1.5 Procedure l/2-0DC-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-FIT101-1, 2RMQ-FIT301-1, 2HVL-FIT112-1 and 2RMQFIT303-1] may be used as comparable alternates when the primary instruments [RM-11 Monitor Item28 for 2HVS-RQ101, 2RMQ-RQ301, 2HVL-RQ112 and 2RMQ-RQ303],
respectively, are INOPERABLE. This is considered an editorial change because the primary monitoring channel (i.e.; RM-11 Monitor Item 28) display already receives its input from these same flow transmitters.
8.2.16.1.6 Procedure l/2-0DC-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-lGW-109 Channel 5] may be used as a comparable alternate to [RM-1GW-108B]
for continuous releases. However, since [RM-lGW-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 approved station documents.
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A..d nf 114 8.2.16.1.7 Procedure l/2-0DC-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:
82.16.2.1 8.2.16.2.2 8.2.16.2.3 8.2.16.2.4 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 Action$ 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.
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.
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.
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.
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A.oCi nf 114 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 l/2-0DC-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.c32*6*9>
8.2.17.1.1.1 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-95-007.(3.23.9> The results of this calculation provide tank specific activity limits to ensure that the 10 CFR 20 Appendix B Table 2, Col. 2 EC Limits will be maintained should an accidental release of the tank(s) contents occur. Previously, LCO 3.1 1. 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.
8.2.17. l.1.2 In addition, individual tank Activity limits were developed for the Unit 1 and 2 Refueling Water Storage Tanks (RWS'rs), which were also added to this ODCM Control. The Surveillance Requirements for determination ofRWST Activity will not be performed once per 7 days like the other Liquid Storage Tanks, because radioactive material is not added to the R WST's on a weekly basis. Therefore, the surveillance for determination of (R WST'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).
8.2.17.1.2 Procedure l/2-0DC-3.03, Rev 1: Changed the due date of the Annual Radioactive Effluent Release Report from April 1 to May 1 as permitted by Unit 1/2 Technical Specification Amendments 1A-250/2A-130.C32*6.9) 8.2.17.1.3 Procedure l/2-0DC-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-lLW-103] on the Liquid Waste Containment Drain Line. This obvious omission is detailed in CR 02-05533.C32212>
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4h ofl14 8.2.17.1.4 Procedure l/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 1A-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-1 and 2 ODCM (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 l/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 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.
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47 of 114 8.2.19 Change (19) ofBV-1 and 2 ODCM (Effective November 2002) 8.2.19.1 A description of the changes implemented with this revision are as follows:
8.2.19.1.1 8.2.19.1.2 8.2.19.1.3 Procedure l/2-0DC-2.01, Rev 1: Changed Table 1.1-la and 1.1-lb 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 027_(3.2.3.t) Addition of Zn-65 to the source terms also caused changes in the Liquid Effluent Monitor Alarm Setpoints, and appropriate monitor conversion factors.
Procedure l/2-0DC-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.(3.2.3.1o)
Procedure l/2-0DC-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.
82.19.2 The justification used for change (19) of the ODCM is as follows:
8.2.19.2.1 Addition of Zn-65 to the BY -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-02-0410. 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) ofBV-1 and 2 ODCM (Effective October 2003) 8.2.20.1 A description of the changes implemented with this revision are as follows:
8.2.20.1.1 8.2.20.1.2 Procedure l/2-0DC-2.01, Rev 2: Changed LW System diagrams (Attachment D) to indicate the flow path for cross connect ofLW between Unit 1 and Unit 2.
Procedure l/2-0DC-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).
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.d.~ of 114 8.220.1.3 8.2.20.1.4 8.2.20.1.5 Procedure l/2-0DC-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-1 VS-110 Ch 7 & Ch 9) was changed FROM "(RM-1VS-107B)" TO "(RM-1VS-107B, orRM-lVS-110 Ch 5)". Also, the 2nd PMM for the Auxiliary Building Ventilation System Mid & High Range Noble Gas Monitors (RM-lVS-109 Ch 7 &
Ch 9) was changed FROM "(RM-lVS-lOlB)" TO "(RM-lVS-lOlB, 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-lGW-109 Ch 7 & Ch 9) was changed FROM "(RM-1GW-108B)" TO
"(RM-1GW-108B, or RM-lGW-109 Ch 5)".
Procedure l/2-0DC-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.
Procedure l/2-0DC-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 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.
8.2.202 The justifications used for change (20) of the ODCM are as follows:
8.2.20.2.1 Procedure l/2-0DC-2.01, Rev 2: Changing the diagram to show the L W cross connect between Unit 1 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 descn"be the cross connect Based on the above, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CFR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
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A.Q of 114 8.2.20.2.2 8.2.20.2.3 Procedure l/2-0DC-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-IIlIM-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.
Procedure l/2-ODC-3.03, Rev 3: Changing the Preplanned Method of Monitoring (PMM) will prevent unnecessary grab sampling (i.e.; 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 (i.e.; obtaining grab gas samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) 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.
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50 of 114 8.2.20.2.4 Procedure l/2-0DC-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. 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 CR 03-07487-05.
8.2.20.2.5 Procedure l/2-0DC-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 effluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR 03-06281-01.
8.2.21 Change (21) ofBV-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 8.2.21.1.2 8.2.21.1.3 8.2.21.1.4 Procedure l/2-0DC-1.01. Rev 4. Procedure l/2-0DC-2.01. Rev 3 and Procedure l/2-0DC-3.03. Rev 4: Changed ownership of procedures from the Radiation Protection Section to the Nuclear Environmental &
Chemistry Section per CR 05-01169-14, CR 05-01169-15 and CR 05-01169-21.
Procedure l/2-0DC-2.01. Rev 3: Changed Attachment D to correct the volume of Liquid Waste Drain Tanks (2LWS-TK21N21B) from 7,500 gal/tank to 10,000 gal/tank.
Procedure l/2-0DC-3.03. Rev 4: Changed Attachment C to implement the increased flexibility in Mode restraints that is described in LAR 1A-321/2A 193 and CR 03-09288-19.
Procedure l/2-0DC-3.03, Rev 4: Corrected a typographical error in, Control 3.11.2.5 per CR03-11726-01. Specifically, the final word in Action (a) was changed from nad" to "and".
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51 nf'l 14 8.2.21.1.5 8.2.21.1.6 8.2.21.1.7 Procedure l/2-0DC-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-lGW-135].
Procedure l/2-0DC-3.03. Rev 4: Revised Attachment F, (Table 3.3-13 and 4.3-13) per CR04-02275-0l. Specifically, clarification was provided to indicate that the Sampler Flow Rate Monitors are the devices used for Particulate and Iodine Sampling".
Procedure l/2-0DC-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:
8.2.21.2.1 8.2.21.2.2 Procedure l/2-0DC-1.01. Rev 4. Procedure l/2-ODC-2.01. Rev 3 and Procedure l/2-0DC-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 CR 05-01169-14, CR 05-01169-15, and CR 05-01169-21.
Procedure l/2-0DC-2.01. 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.
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~?. nf 114 8.2.21.2.3 8.2.21.2.4 8.2.21.2.5 8.2.21.2.6 Procedure l/2-ODC-3.03, Rev 4: Changing Attachment C to implement the increased flexibility in Mode restraints (described in LAR 1A-321/2A-193) is considered a simple change. SINCE the change implements guidance provided in the Technical Specifications, TIIEN the change will maintain the level of radioactive e:flluent 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 eflluent dose or alarm setpoint calculation.
This procedure change implements a Corrective Action per CR 03-09288-19.
Procedure l/2-0DC-3.03, Rev 4: The typographical error in, Control 3.11.2.5 is considered a procedure correction.
Therefore, this change will maintain the level of radioactive eflluent 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 eflluent dose or alarm setpoint calculation.
This procedure change implements a Corrective Action per CR 03-11726-01.
Procedure l/2-0DC-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 merely corrects an obvious error, 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 CPR 50. Also, this change will not impact the accuracy or reliability of effiuent dose or alarm setpoint calculation.
This procedure change implements a Corrective Action per CR04-01643-0 l.
Procedure l/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 eflluent release calculations or offsite dose determinations, THEN this change will maintain the level of radioactive e:flluent 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 e:flluent dose or alarm setpoint calculation. This procedure change implements a Corrective Action per CR04-022 7 5-0 I.
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.:;1 nf 114 8.2.21.2.7 Procedure l/2-0DC-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 indiyidual 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-95-007 (3.2.3.9>, 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.
8.2.22 Change (22) ofBV-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 8.2.22.1.2 8.2.22.1.3 Procedure l/2-0DC-2.01, Rev 4: Incorporatecflmproved Technical Specification Reference changes from T.S. 6.8.6 to T.S. 5.5.2, per CR 05-03306. Revised the alarm setpoints of [RM-lRM-100] and
[RM-lDA-100] 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 CR 06-04908-03.
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 CR 05-03854-01.
Procedure l/2-0DC-2.02, Rev 2: Changed ownership of procedure from the Radiation Protection Section to the Nuclear Environmental &
Chemistry Section per CR 05-01169-16. Incorporated a "S' 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 CR 06-04908-
- 04.
Procedure l/2-0DC-3.03, Rev 5: 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 CR 06-04908-03.
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~A. nf 114 8.2.22.2 The justifications used for change (22) of the ODCM are as follows:
8.2.22.2.1 8.2.22.2.2 8.2.22.2.3 Procedure l/2-0DC-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 l/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 CR 06-04908-03, and CR 05-03854-
- 01.
Procedure l/2-0DC-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 CR 05-01169-16 and CR 06-04908-04.
Procedure l/2-0DC-3.03, 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 CPR 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, TIIEN 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 CR 06-04908-03.
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"" of 114 8.2.23 Change (23) ofBV-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 l/2-0DC-1.01. Rev 5: Changed Attachment C, Table F: 3a of the procedure matrix to add Form 1/2-ENV-01.04.F0l as documentation for performing a Channel Functional Test of the Unit 1 Primary and Alternate Gaseous Effluent Sampler Flowrate Measuring Devices per CR 04-09895. 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.F0l & F02) per CR 05-01422. 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 CR 05-03306.
8.2.23.1.2 Procedure l/2-ODC-2.01. Rev 5: Revised the alarm setpoints of
[2SWS-RQ101] via vendor calculation Package No. 10080-UR(B)-508.
These changes reflect the Ex.tended Power Uprate (EPU) at Unit 2 per ECP-04-0441, Unit 2 TS Amendment No. 156 and CR 06-6476-01.
8.2.23.1.3 Procedure l/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 CR 05-01390-02.
8.2.23.1.4 Procedure l/2-ODC-3.02. Rev 2: Changed ownership of procedure from the Radiation Protection Section to the Nuclear Environmental &
Chemistry Section per CR 05-01169-20.
8.2.23.1.5 Procedure l/2-0DC-2.03. Rev I. Procedure l/2-ODC-2.04. Rev 1 and Procedure l/2-0DC-3.01. Rev 1: Changed ownership of procedures from the Radiation Protection Section to the Nuclear Environmental &
Chemistry Section per CR 05-01169-17, CR 05-01169-18 and CR 06-01169-19.
)
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"" n-f 114 8.223.2 Tue justifications used for change (23) of the ODCM are as follows:
8.2.23.2.1 8.2.23.2.2 8.2.23.2.3 Procedure 1/2-0DC-l.0l. Rev 5: Changing Attachment C, Table F: 3a of the procedure matrix to add Form 1/2-ENV-01.04.FOl as documentation for performing the Channel Functional Test of the Unit 1 Primary and Alternate Gaseous Eflluent Sampler Flowrate Measuring Devices is considered a procedure correction, because no Acceptance Criteria was altered. Transition ofODCM Channel Checks from Operations (LS Logs) to Nuclear Environmental & Chemistiy (Form 1/2-ADM-0606.F0 1 & F02) is also considered a procedure correction, because the no Acceptance Criteria was altered. SINCE these changes merely correct the procedure matrix, TIIEN the changes will maintain the level of radioactive eflluent 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 CR 04-09895, CR 05-01422 and CR 05-03306.
Procedure l/2-0DC-2.01, 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 1 OCFR 50. Also, the change will not impact the accuracy or reliability of eflluent dose or alarm setpoint calculation.
SINCE PORC review & acceptance is required perTS 6.14 & 1/2-ADM-1640, THEN the review is considered complete per Regulatoiy Applicability Determination RAD-06-04585. As previously noted, these procedure changes implement Corrective Actions per CR 06-6476-0 l.
Procedure l/2-0DC-2.03. Rev 1: Updating the existing REMP sampling locations with the most recent smvey 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 eflluent 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. Tue procedure change implements Corrective Actions per CR 04-00149-12 and CR 05-01390-02.
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t:,7 of 114 8.2.23.2.4 Procedure l/2-0DC-2.03, Rev 1, Procedure l/2-0DC-2.04, Rev 1 and Procedure l/2-0DC-3.01, Rev 1: Changing ownership of these procedures from Radiation Protection to Nuclear Environmental &
Chemistry is considered a procedure correction. SINCE the changes merely traru;fers RETS, REMP and ODCM responsibilities to a different manager, TIIEN 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 CR 05-01169-17, CR 05-01169-18 and CR 06-01169-19.
8.2.24 Change (24) ofBV-1 and 2 ODCM (Effective May 2007) 8.2.24.1 A description of the changes implemented with this revision are as follows:
8.2.24.1.1 8.2.24.1.2 8.2.24.1.3 8.2.24.1.4 8.2.24.1.5 Procedure l/2-0DC-3.03, Rev 6: Incorporated Improved Technical Specifications (ITS). This includes transfer of programmatic controls for BV-2 Noble Gas Effluent Steam Monitors [2MSS-RQ101A],
[2MSS-RQ101B] and [2MSS-RQ101C] from the Technical Specifications to ODCM procedure l/2-0DC-3.03 (Attachment D Tables 3.3-6 and 4.3-3). Reference CR 05-03306.
Procedure l/2-0DC-3.03, Rev 6: Revised Attachment J to update the outside liquid storage tank activity limits via Calculation Package No. ERS-ATL-95-007, R2. Reference SAP Order 200197646-0110.
Procedure l/2-0DC-3.03, Rev 6: Revised Attachment E to clarify that the Applicability for tank level indicating devices is during additions to the tank. Reference CR 06-04944.
Procedure l/2-ODC-3.03, Rev 6: Revised Attachment E Table 3.3-12 to add an alternate Action when the primary Flow Rate Measurement Device [FT-lCW-101-1] is not OPERABLE. The alternate Action (25) uses local measurements (as descnbed in lMSP-31.06-I) to determine a total dilution flow rate during liquid effluent releases. Reference SAP Order 200240681.
Procedure l/2-0DC-3.03, Rev 6: Revised Attachment F Tables 3.3-13 and 4.3-13 to clarify the Functional Location of the Sampler Flow Rate Monitors for the BV-2 gaseous effluent release pathways. Specifically, the procedure was changed to refer to Functional Location [2HVS-FIT101-1] instead of [2HVS-FIT101], [2RMQ-FIT301-1] instead of
[2RMQ-FIT301], [2HVL-FIT112-1] instead of [2HVL-FIT112], and
[2RMQ-FIT303-l] instead of [2RMQ-FIT303]. Reference CR07-12924 and SAP Order 200247228-0410.
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-SR nfl 14 8.2.24.2 The justifications used for change (24) of the ODCM are as follows:
8.2.24.2.1 8.2.24.2.2 8.2.24.2.3 Procedure l/2-0DC-3.03. Rev 6: Incorporating the Improved Technical Specifications {ITS) is considered a simple change, because this was performed in accordance with the guidance provided in Unit 1/2 Technical Specification Amendments No. 278/161. The ITS upgrade includes transfer of programmatic controls for BV-2 Noble Gas Effluent Steam Monitors [2MSS-RQ101A], [2MSS-RQ101B] and
[2MSS-RQ101C] from the Technical Specifications to ODCM procedure l/2-0DC-3.03 (Attachment D Tables 3.3-6 and 4.3-3.
SINCE the change was performed in accordance with the TS Amendments, TIIBN the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 4-0 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. PORC review and acceptance of this change was completed in May 2007. The procedure change implements Corrective Actions per CR 05-03306.
Procedure l/2-0DC-3.03. Rev 6: Revising Attachment J to update the outside liquid storage tank activity limits via Calculation Package No. ERS-ATL-95-007, R2 is considered a simple change, because this change merely implements updated release volumes and source-terms from other station documents. SINCE the change was performed in accordance with the guidance provided in Standard Review Plan 15.7.3 of NUREG-0800, 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. PORC review and acceptance of this change was completed in May 2007. The procedure change implements Corrective Actions per SAP Order 200197646-0110.
Procedure l/2-0DC-3.03. Rev 6: Revising Attachment E to indicate that the Applicability for tank level indicating devices is during additions to the tank is considered a simple change, because this merely clarifies the existing Applicability of the instrument. SINCE this change merely provides clarification of existing Applicability, 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.
PORC review and acceptance of this change was completed in May 2007. The procedure change implements Corrective Actions per CR 06-04944-01.
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59 ofl 14 8.2.24.2.4 Procedure l/2-0DC-3.03, Rev 6: Revising Attachment E Table 3.3-12 to add an alternate Action when the primary Flow Rate Measurement Device [FT-ICW-101-1] is not OPERABLE is considered a simple change, because use of an alternate Action does not modify the in~t of estimating flow rate when the primary and alternate flow rate instruments are not OPERABLE. SINCE this change merely provides an alternate means of estimating dilution flow rate during liquid releases, 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.
PORC review and acceptance of this change was completed in May 2007. The procedure change implements Corrective Actions per SAP Order 200240681.
8.2.24.2.5 Procedure l/2-0DC-3.03. Rev 6: Revising Attachment F Tables 3.3-13 and 4.3-13 to clarify the Functional Location of the Sampler Flow Rate Monitors for the BV-2 gaseous eftluent release pathways is considered a simple change, because this merely clarifies the actual Functional Location in use. SINCE this change merely updates a location title, THEN the change will maintain the level of radioactive eftluent 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.
PORC review and acceptance of this change was completed in May 2007. The procedure change implements Corrective Actions per CR 07-12924 and SAP Order 200247228--0410.
8.2.25 Change (25) ofBV-1 and 2 ODCM (Effective May 2009) 8.2.25.1 A description of the changes implemented with this revision are as follows:
8.2.25.1.1 8.2.25.1.2 Procedure l/2-0DC-1.01 Rev 7: Removed the requirement for PORC review and acceptance of changes made to the ODCM.
Procedure 1/2-0DC-1.0l. Rev 7: Added MSP and OST references for EPP-EAL area and process monitors to Attachment C, Table F: la and lb. Specifically, this includes area monitors RM-IRM-201, RM-IRM-202, RM-IRM-203, RM-IRM-210, RM-IRM-212, 2RMP-RQ204, 2RMP-RQ210, 2Rl\\1R-RQ201, 2RMR-RQ202B, 2RMR-RQ203, 2RMS-RQ223, and process monitors RM-lCH-lOIA, RM-lCH-l0IB, RM-lRW-lO0A, RM-lRW-lOOB, RM-lRW-lO0C, RM-IRW-100D, RM-1VS-103A, RM-1VS-103B, 2CHS-RQ101A, 2CHS-RQ101B, 2SWS-RQI00A, 2SWS-RQI00B, 2SWS-RQI0OC, 2SWS-RQ100D, 2SWS-RQ101, 2SWS-RQ102, 2RMF-RQ301A, 2RMF-RQ301B.
Reference CR09-53803-13.
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f.() nf 114 8.2.25.1.3 Procedure 1/2-0DC-1.0l. Rev 7: Revised Attachment C Tables of the procedure matrix to remove obsolete forms and procedures used for ODCM Channel Checks. Specifically, Form l/2-ADM-0606.F0I, Form 1/2-ADM-0606.F02, Form l/2-HPP-3.07.003.F0I and procedures l/2-HPP-3.06.005, l/2-HPP-3.06.006 & l/2-HPP-3.06.012 were removed from the procedure matrix. Reference SAP Order 200257692-0360 and 0390.
8.2.25.1.4 Procedure l/2-0DC-2.01. Rev 6: Added the Coolant Recovery Tanks
[1BR-TK-4A/4B] as Liquid Waste Tanks to Section 8.4 description and Attachment D Figures 1.4-1 and 1.4-2. Added a default 2-tank volume recirculation time of 45. 7 hrs for the Coolant Recovery Tanks
[1BR-TK-4A/4B] to Attachment B Table 1.2-la. Added the Cesium Removal Ion Exchangers [lBR-I-lA/lB and 2BRS-IOE21A/21B] to Section 8.4 description and Attachment B Figures 1.4-1 and 1.4-2.
Revised the recirculation times in Attachment B Table 1.2-1 a and 1.2-1 b to indicate the times for nominal tank volume and maximum tank volume. Reference CR 05-00004-15, CR 05-00004-17 and SAP Order 200197646-0010.
8.2.25.1.5 Procedure l/2-0DC-2.01, Rey 6: Revised Attachment D Figure 1.4-3 to remove Sewage Treatment Plants (STP) Outfalls 113 and 203 due to retirement of the STP and to remove Outfall 501. Water is no longer discharged via these outfalls. Reference SAP Order 200197646-0660.
8.2.25.1.6 Procedure l/2-ODC-2.01, Rev 6: Revised section 8.1.1.1 to incorporate alarm setpoints for all possible detector combinations for [RM-IDA-100]. Specifically, due to obsolescence of the original Model 843-30 and 843-32 detectors that were previously installed in [RM-IDA-100],
the vendor has upgraded them to Model 843-30R and 843-32R detectors, which include upgraded efficiency data as well. Reference SAP Order 200197646-0810.
8.2.25.1.7 Procedure l/2-ODC-3.03, Rev 7: Added EPP-EAL area and process monitors to Attachment D, Tables 3.3-6 and 4.3-3. Specifically, this includes area monitors RM-IRM-201, RM-IRM-202, RM-IRM-203, RM-IRM-210, RM-IRM-212, 2RMP-RQ204, 2RMP-RQ210, 2RMR-RQ201, 2RMR-RQ202B, 2RMR-RQ203, 2RMS-RQ223, and process monitors RM-lCH-lOIA, RM-ICH-IOIB, RM-IRW-IO0A, RM-IRW-IO0B, RM-IRW-IOOC, RM-IRW-100D, RM-1VS-103A, RM-I VS-103B, 2CHS-RQ101A, 2CHS-RQ101B, 2SWS-RQIO0A, 2SWS-RQ 1 00B, 2SWS-RQ 1 0OC, 2SWS-RQ 100D, 2SWS-RQ 101, 2SWS-RQ102, 2RMF-RQ301A, 2RMF-RQ301B. Other editorial changes included adding EAL references to existing liquid and gaseous radiation monitors provided in Attachment E and Attachment F, respectively. Reference CR 09-53803-10.
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61 nf 114 8.2.25.1.8 Procedure l/2-ODC-3.03, Rev 7: Added a definition for Channel Functional Test and revised the definition for Channel Operational Test to indicate that these definitions have the same requirements and, therefore, are considered equal. Reference SAP Order 200197 646-0300 and CR 07-31083.
8.2.25.1.9 Procedure l/2-ODC-3.03, Rev 7: Revised Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added clarifications and to remove unnecessary information, as follows: (1) added the word "or" where it is missing from Attachment F, Table 3.3-13 & 4.3-13, (2) removed grab samples from the list of alternates in Table 3.3-13 and 4.3-13, because a grab sample is an "action", not an "alternate", (3) added notations in Table 3.3-12 and 3.3-13 to indicate that Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action band 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days, and (4) removed surveillances for Preplanned Method of Monitoring (PMM) from Table 4.3-3, because surveillances only apply to instruments, not methods. Reference SAP Order 200247228-0450.
8.2.25.1.10 Procedure l/2-0DC-3.03, Rev 7: Revised Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1st and 2nd alternates to the flow rate measurement devices used for the cooling tower blowdown line. Specifically, 1st alternate will use local measurements via lMSP-31.06-I, and the 2nd alternate will use the individual Units' devices.
Reference SAP Order 200240681-0020.
8.2.25.2 The justifications used for change (25) of the ODCM are as follows:
8.2.25.2.1 8.2.25.2.2 Procedure 1/2-0DC-l.0l Rev 7: Removed the requirement for PORC review and acceptance of changes made to the ODCM as it is no longer a requirement of ITS 5.5.1.
Procedure l/2-0DC-1.01, Rev 7: Adding MSP and OST references for EPP-EAL area and process monitors to Attachment C, Table F: la and 1 b does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per CR 09-53803-13.
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r..? of 114 8.2.25.2.3 8.2.25.2.4 8.2.25.2.5 Procedure l/2-0DC-1.01. Rev 7: Revising Attachment C Tables of the procedure matrix to remove obsolete forms and procedures used for ODCM Channel Checks does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200257692-0360 and 0390.
Procedure l/2-0DC-2.01, Rev 6: Adding; (1) the Coolant Recovery Tanks as Liquid Waste Tanks, (2) adding a default 2-tank volume recirculation time for the Coolant Recovery Tanks, (3) adding the Cesium Removal Ion Exchangers, and (4) revising the recirculation times to indicate the times for nominal tank volume and maximum tank volume does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per CR05-00004-15, CR05-00004-l 7 and SAP Order 200197646-0010.
Procedure l/2-0DC-2.01. Rev 6: Revising Attachment D Figure 1.4-3 to remove Sewage Treatment Plants (STP) Outfalls 113 and 203 does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200197646-0660.
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l.l nf"l 14 8.2.25.2.6 Procedure l/2-0DC-2.01, Rev 6: Revising Section 8.1.1.1 to incorporate alarm setpoints for all possible detector combinations for
[RM-lDA-100] does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200197646-0810.
8.2.25.2.7 Procedure l/2-0DC-3.03, Rev 7: Adding EPP-EAL area and process monitors to Attachment D, Tables 3.3-6 and 4.3-3 (and adding EAL references to existing liquid and gaseous radiation monitors Attachment E and Attachment F) does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per CR 09-53803-10.
8.2.25.2.8 Procedure l/2-0DC-3.03, Rev 7: Adding a definition for Channel Functional Test and revising the definition for Channel Operational Test to indicate that these definitions have the same requirements (i.e.,
considered equal) does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200197646-0300 and CR 07-31083.
8.2.25.2.9 Procedure l/2-0DC-3.03, Rev 7: Revising Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added clarifications and to remove unnecessary information does not remove or modify any standard ODCM Controls specified in NUREG-1301.
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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200247228-0450.
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h4 of 114 8.2.25.2.10 Procedure l/2-0DC-3.03, Rev 7: Revising Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1st and 2nd alternates to the flow rate measurement devices used for the cooling tower blowdown line does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in May 2007. This change implements Corrective Actions per SAP Order 200240681-0020.
8.2.26 Change (26) ofBV-1 and 2 ODCM (Effective May 2009) 8.2.26.1 A description of the changes implemented with this revision are as follows:
8.2.26.1.1 82.26.1.2 8.2.26.1.3 Procedure l/2-0DC-1.01 Rev 8: Reverted procedure back to the contents of Revision 6.
Procedure l/2-0DC-2.01, Rev 7: Reverted procedure back to the contents of Revision 5.
Procedure l/2-0DC-3.03, Rev 8: Reverted procedure back to the contents of Revision 6.
8.2.26.2 The justifications used for change (26) of the ODCM are as follows:
82.26.2.1 8.2.26.2.2 8.2.26.2.3 Procedure l/2-0DC-1.01 Rev 8: It was determined that the implementation of Revision 7 was premature because supporting procedure changes were not completed and surveillances required by these changes were not in place. This procedure was reverted back to the contents of the previous revision. This change implements Corrective Actions initiated by and described in CR 09-59875.
Procedure l/2-0DC-2.01, Rev 7: It was determined that the implementation of Revision 6 was premature because supporting procedure changes were not completed and surveillances required by these changes were not in place. This procedure was reverted back to the contents of the previous revision. This change'implements Corrective Actions initiated by and described in CR 09-59875.
Procedure l/2-0DC-3.03, Rev 8: It was determined that the implementation of Revision 7 was premature because supporting procedure changes were not completed and surveillances required by these changes were not in place. This procedure was reverted back to the contents of the previous revision. This change implements Corrective Actions initiated by and described in CR 09-59875.
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"" nf 114 8.2.27 Change {27) ofBV-1 and 2 ODCM {Effective August 2010) 8.2.27.l A description of the changes implemented with this revision are as follows:
8.2.27.1.1 Procedure l/2-0DC-1.01, Rev 9: Added revision history to capture Changes 25 and 26.
8.2.27.1.2 Procedure l/2-ODC-1.01, Rev 9: Removed the requirement for PORC review and acceptance of changes made to the ODCM.
8.2.27.1.3 Procedure l/2-ODC-1.01, Rev 9: Revised Attachment C Tables of the procedure matrix to remove obsolete forms and procedures used for ODCM Channel Checks. Specifically, Form l/2-ADM-0606.F0l, Form l/2-ADM-0606.F02, Form 1/2-HPP-3.07.003.F0l and procedures 1/2-HPP-3.06.005, l/2-HPP-3.06.006 were removed from the procedure matrix (superseded by 1/2-ADM-161 l.F03, l/2-ADM-161 l.F04, NOP-OP-4702-01, l/2-ENV-05.04, and 1/2-ENV-05.05, respectively). Reference SAP Order 200257692-0360 and 0390.
References were updated for Operational Surveillance Tests (OSTs) for Channel Functional Tests that have since been split from one large OST into specific OSTs for each radiation monitor and obsolete Chemistry and Environmental procedures.
8.2.27.1.4 Procedure l/2-0DC-2.01, Rev 8: Revised Attachment D Figure 1.4-3 to remove Sewage Treatment Plants (STP) Outfalls 113 and 203 due to retirement of the STP and to remove Ul Steam Generator Blowdown Filter Backwash Outfall 501. Water is no longer discharged via these outfalls. Reference SAP Order 200197646-0660.
8.2.27.1.5 Procedure l/2-0DC-2.01, Rev 8: Revised section 8.1.1.1 to incorporate alarm setpoints for all possible detector combinations for [RM-lDA-100]. Specifically, due to obsolescence of the original Model 843-30 and 843-32 detectors that were previously installed in [RM-lDA-100],
the vendor has upgraded them to Model 843-30R and 843-32R detectors, which include upgraded efficiency data as well. Reference SAP Order 200197646-0810.
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'1'1 nf 114 8.2.27.1.6 Procedure 1/2-0DC-2.01, Rev 8: Added the Coolant Recovery Tanks
[1BR-TK.-4A/4B] as Liquid Waste Tanks to Section 8.4 description and Attachment D Figures 1.4-1 and 1.4-2. Added a default 2-tank volume recirculation time of 45. 7 hrs for the Coolant Recovery Tanks
[1BR-TK.-4A/4B] to Attachment B Table 1.2-la. Added the Cesium Removal Ion Exchangers [lBR-I-lA/lB and 2BRS-IOE21A/21B] to Section 8.4 description and Attachment B Figures 1.4-1 and 1.4-2.
Revised the recirculation times in Attachment B Table 1.2-1 a and 1.2-1 b to indicate the times for nominal tank volume and maximum tank volume. Reference CR 05-00004-15, CR 05-00004-17 and SAP Order 200197646-0010.
8.2.27.1.7 Procedure l/2-0DC-2.03, Rev 2: Corrected sampling location descriptions for TLD #94 and #95; Changed sample designation from
- 49 to #49A; Clarified program requirements for garden sampling.
These changes implement Corrective Actions for CA #10-77489-1.
8.2.27.1.8 Procedure l/2-0DC-3.03, Rev 9: Added a definition for Channel Functional Test and revised the definition for Channel Operational Test to indicate that these definitions have the same requirements and, therefore, are considered equal. Reference SAP Order 200197 646-0300 and CR07-31083.
8.2.27.1.9 Procedure l/2-0DC-3.03, Rev 9: Revised Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added clarifications and to remove unnecessary information, as follows: (1) added the word "or" where it is missing from Attachment F, Table 3.3-13 & 4.3-13, (2) removed grab samples from the list of alternates in Table 3.3-13 and 4.3-13, because a grab sample is an "action", not an "alternate", (3) added notations in Table 3.3-12 and 3.3-13 to indicate that Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action band 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days, and (4) removed surveillances for Preplanned Method of Monitoring (PMM) from Table 4.3-3, because surveillances only apply to instruments, not methods. Reference SAP Order 200247228-0450.
8.2.27.1.10 Procedure l/2-0DC-3.03, Rey 9: Revised Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1 111 and 2nd alternates to the flow rate measurement devices used for the cooling tower blowdown line. Specifically, 1st alternate will use the individual Units' devices, and the 2nd alternate will use local measurements via lMSP-31.06-I.
The alternates were chosen in this particular order to support practicality of plant operations, rather than the way they were initially proposed in the SAP order. Reference SAP Order 200240681-0020.
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67 nf114 8.2.27.1.11 Procedure l/2-0DC-3.03, Rev 9: Revised Attachment D Tables 3.3-6 and 4.3-3 to remove obsolete forms and procedures Specifically, Form 1/2-ENV-05.14.F0l was removed.
8.2.27.2 The justifications used for change (27) of the ODCM are as follows:
8.2.27.2.1 8.2.27.2.2 8.2.27.2.3 8.2.27.2.4 Procedure l/2-0DC-1.01 Rev 9 : Because it was determined that the implementation of Revision 7 was premature and this procedure was reverted back to the exact contents of the previous revision, the revision history was not captured. PORC review and acceptance of this change was completed in August 2010.
Procedure l/2-0DC-1.01, Rev 9: Removed the requirement for PORC review and acceptance of changes made to the ODCM as it is no longer a requirement of ITS 5.5.1. PORC review and acceptance of this change was completed in August 2010.
Procedure l/2-0DC-1.01, Rev 9: Revising Attachment C Tables of the procedure matrix to remove obsolete forms and procedures does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive,
effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
This change implements some of the corrective actions per SAP Order 200257692-0360 and 0390. PORC review and acceptance of this change was completed in August 2010.
Procedure l/2-0DC-2.01, Rev 8: Revising Attachment D Figure 1.4-3 to remove Sewage Treatment Plants (STP) Outfalls 113 and 203 and Ul Steam Generator Blowdown Filter Backwash Outfall 501 does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per SAP Order 200197646-0660.
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l'IR nf 114 8.2.27.2.5 8.2.27.2.6 8.2.27.2.7 8.2.27.2.8 Procedure l/2-0DC-2.01, Rev 8: Revising Section 8.1.1.1 to incorporate alarm setpoints for all possible detector combinations for
[RM-lDA-100] does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive eftluent 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 eftluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per SAP Order 200197646-0810.
Procedure l/2-0DC-2.01, Rev 8: Adding; (1) the Coolant Recovery Tanks as Liquid Waste Tanks, (2) adding a default 2-tank volume recirculation time for the Coolant Recovery Tanks, (3) adding the Cesium Removal Ion Exchangers, and (4) revising the recirculation times to indicate the times for nominal tank volume and maximum tank volume does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive eftluent 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 eftluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per CR 05-00004-15, CR 05-00004-17 and SAP Order 200197646-0010.
Procedure l/2-0DC-2.03, Rev 2: All changes in this revision were to correct labeling deficiencies. They did not change program requirements or the implementation of program sampling. There is no impact to the accuracy or reliability of the Radiological Environmental Monitoring Program. This change implements Corrective Action 10-77489-1. PORC review of these changes was completed on August 2010.
Procedure l/2-0DC-3.03, Rev 9: Adding a definition for Channel Functional Test and revising the definition for Channel Operational Test to indicate that these definitions have the same requirements (i.e.,
considered equal) does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per SAP Order 200197646-0300 and CR 07-31083.
I
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I.Q nf 114 8.2.27.2.9 Procedure l/2-0DC-3.03. Rev 9: Revising Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added clarifications and to remove unnecessary information does not remove or modify any standard ODCM Controls specified in NUREG-1301.
Therefore, this change will maintain the level of radioactive eflluent 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.
PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per SAP Order 200247228-0450.
8.2.27.2.10 Procedure l/2-0DC-3.03. Rev 9: Revising Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1st and 2nd alternates to the flow rate measmement devices used for the cooling tower blowdown line does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CFR Part 190, 10 CPR 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. PORC review and acceptance of this change was completed in August 2010. This change implements Corrective Actions per SAP Order 200240681-0020.
8.2.27.2.11 Procedure l/2-0DC-3.03. Rev 9: Revising Attachment D Tables to remove obsolete forms and procedures does not remove or modify any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CPR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CPR 50. Also, the change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. PORC review and acceptance of this change was completed in August 2010.
8.2.28 Change (28) ofBV-1 and 2 ODCM (Effective December 2010) 8.2.28.1 A description of the changes implemented with this revision are as follows:
8.2.28.1.1 8.2.28.1.2 Procedure l/2-0DC-1.01. Rev 10: Revision history was updated and references to CTS and ITS conversion project were removed.
Procedure l/2-0DC-2.01. Rev 9: Removed description that batch releases of liquid waste are processed by recirculation through eductors.
Deleted Attachment B which referenced minimum liquid waste batch release recirculation times and added description that liquid waste recirculation times to achieve two tank volumes are calculated based upon actual tank volume and pump capacity.
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70 nf 114 8.2.28.2 The justifications used for change (28) of the ODCM are as follows:
8.2.28.2.1 8.2.28.2.2 Procedure l/2-0DC-1.01 Rev 10: Changes are administrative only because ITS conversion project has been completed. 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.
Procedure l/2-0DC-2.01 Rev 9: Change removes description that batch releases of liquid waste be recirculated through tanks with eductors.
Eductors are not currently installed on liquid waste tanks. Per BVPS-1 UFSAR Section 1.3.3.21, the recommendations contained in Regulatory Guide 121 (1974) are followed. The RG states that (prior to sampling) "large volumes of liquid waste should be mixed in as short a time interval as practicable to assure that any sediments or particulate solids are distnbuted uniformly in the waste mixture." BVPS-2 UFSAR Table 1.8-1 contains a similar statement As such, current licensing bases does not require eductors for processing batch releases of liquid waste. Attachment B was removed. This attachment provided information on minim1Jm recirculation times of liquid waste tanks for batch liquid releases. Recirculation times are calculated based upon actual tank volume and pump capacity and this description was added.
The change does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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.
8.2.29 Change (29) ofBV-1 and 2 ODCM {Effective January 2011) 8.2.29.1 A description of the changes implemented with this revision are as follows:
8.2.29.1.1 Procedure l/2-ODC-2.02. Rev 3: This revision corrected a spelling error in the title of Attachment C. A typo was corrected in equation 2.2-13. Calculated values of the organ dose parameters, Pi-r, listed in Table 2.2-13 were verified to have been accurately calculated using the breathing rate of 3.7E9 in Calculation Package No. ERS-HHM-84-20, ODCM Update of Table 2.2-1S and Calculation Package No. ERS-ATL-89-014, Verification/Validation of ODCM R Values. Dose factors for Selenium-75 (Se-75) were provided by ABS Consulting.
Attachment H (Table 2.2-13) and Attachment J (Tables 2.3-2 through 2.3-20) were copied into excel/word format and updated to include Se-75.
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71 of 114 8.2.29.1.2 Procedure l/2-0DC-3.03 Rev 10: The previous revisions to the
_procedure (Change 25, Revision 7 and then again in Change 27, Revision 9) added notations in Table 3.3-12 and 3.3-13 to indicate that Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action b and 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days. However, Control 3.3.3.9 Action b and 3.3.3.10 Action b provided conflicting guidance because the footnote was not included on these pages. Therefore, the footnote was added to Control 3.3.3.9 Action band 3.3.3.10 Action bin this revision.
8.2.29.2 The justifications used for change (29) of the ODCM are as follows:
8.2.29.2.1 8.2.29.2.2 Procedure l/2-0DC-2.02, Rev 3: This change corrects a minor typo and adds an isotope to the program. The change does not remove or modify any standard ODCM Controls specified in NUREG-1301.
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.
Procedure l/2-0DC-3.03 Rev 10: Revising the Controls for Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 to provide added clarification does not remove or modify any standard ODCM Controls currently in place. 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.
8.2.30 Change (30) ofBV-1 and 2 ODCM (Effective September 2011) 8.2.30.1 A description of the changes implemented with this revision are as follows:
8.2.30.1.1 Procedure l/2-0DC-2.03. Rev 3: This change retired 1LD Station #88 and added Station #88A according to CA G203-2011-97516-001 due to repeated vandalism of the sample point.
8.2.30.2 The justifications used for change (29) of the ODCM are as follows:
8.2.30.2.l Procedure l/2-0DC-2.03, Rev 3: This revision exchanges two sample locations within the same sector, therefore maintaining the same total number of monitoring points located around BVPS. The change does not remove or modify any standard ODCM Controls specified in NUREG-1301. 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.
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72 nf 114 8.2.31 Change (31) ofBV-1 and 2 ODCM (Effective December 2011) 8.2.31.1 A description of the changes implemented with this revision are as follows:
8.2.31.1.1 8.2.31.1.2 Procedure l/2-0DC-2.03, Rev 4: This revision increases vegetation s~pling requirements when milk sampling requirements cannot be met due to milk sampling locations being unavailable.
Procedure l/2-0DC-3.03, Rev 11: This revision increases vegetation sampling requirements when milk sampling requirements cannot be met due to milk sampling locations being unavailable.
8.2.31.2 The justifications used for change (31) of the ODCM are as follows:
8.2.31.2.1 8.2.31.2.2 Procedure l/2-0DC-2.03, Rev 4: Because of decreasing milk locations in the vicinity ofBVPS, the REMP needed to be revised to provide instructions for sampling when we do not have enough milk locations to meet ODCM requirements. The vegetation sampling program is in accordance with NUREG-1301. The change does not remove any standard ODCM Controls specified in NUREG-,1301. 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 CFR50.
Procedure l/2-0DC-3.03, Rev 11: Because of decreasing milk locations in the vicinity ofBVPS, the REMP needed to be revised to provide instructions for sampling when we do not have enough milk locations to meet ODCM requirements. The vegetation sampling program is in accordance with NUREG-1301. The change does not remove any standard ODCM Controls specified in NUREG-1301.
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.
8.2.32 Change (32) ofBV-1 and 2 ODCM {Effective February 2012) 8.2.32.1 A description of the changes implemented with this revision are as follows:
8.2.32.1.1 Procedure l/2-0DC-2.01, Rev 10: This revision implements changes to the Liquid Rad Waste System per ECP 11-0049 in order to continue improvements to the system after the site added the Coolant Recovery Tanks [BR-TK-4A/B] to the liquid waste system in revision 8 (ODCM Change 27). Other descriptions to the liquid waste system components were revised to better reflect actual plant conditions (for ex.ample, normal rate of discharge through the radiation monitor for BR-TK-4A/B or the resin selection/sequence for LW-I-2).
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73 nf 114 8.2.32.2 The justifications used for change (32) of the ODCM are as follows:
8.2.32.2.1 Procedure l/2-0DC-2.01, Rev 10: This change provides a description of the Rad Waste System. It does not remove any standard ODCM Controls specified in NUREG-1301. 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.
8.2.33 Change (33) ofBV-1 and 2 ODCM (Effective June 2012) 8.2.33.1 A description of the changes implemented with this revision are as follows:
8.2.33.1.1 Procedure l/2-0DC-2.01. Rev 11: This revision adds Antimony-126 (Sb-126) to Attachment B Table 1.3-1, Ingestion Dose Commitment Factors, after the isotope was identified during 1R21.
After revising ERS-ATL-83-027, the calculation package for liquid Ingestion Dose Commitment Factors, it was noticed that other isotopes previously calculated in the package were not included in Attachment B. These were also added to the ODCM at this time. The revision also reduces the IIlISP and HSP for Unit 1 Radiation Monitor RM-RW-100 per Calculation Package ERS-ATL-93-021 Rev. 4.
8.2.33.2 The justifications used for c~ge (33) of the ODCM are as follows:
8.2.33.2.1 Procedure l/2-0DC-2.01. Rev 11: This change added the ability to calculate dose for additional isotopes and lowered the alarm setpoints for a radiation monitor. It did not remove any standard ODCM Controls specified in NUREG-1301. 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.
8.2.34 Change (34) ofBV-1 and 2 ODCM (Effective July 2012) 8.2.34.1 A description of the changes implemented with this revision are as follows:
8.2.34.1.1 Procedure l/2-0DC-1.01, Rev 16: Removed reference to analytical procedure 1/2-ENV-0525. This procedure is slated for deletion in the near future.
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74 nfl 14 8.2.34.1.2 Procedure l/2-0DC-2.01, Rev 12: This revision adds the ability to discharge processed and unprocessed liquid wastes from the low level drains tanks [LW-TK-3A/B]. These tanks were originally designed with the ability to discharge to the Ohio River. They are not generally used due to their small volume capacity. A request was made by Operations to allow discharge of these tanks to prevent unnecessary damage/depletion of the liquid waste ion exchanger(s) from non-radioactive water containing high chemical contaminants.
8.2.34.2 The justifications used for change (34) of the ODCM are as follows:
8.2.34.2.1 8.2.34.2.2 Procedure l/2-0DC-1.01, Rev 16: This change removed a reference throughout the document It did not remove any standard ODCM Controls specified in NUREG-1301. 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.
Procedure l/2-0DC-2.01, Rev 12: This change added the ability to discharge processed and unprocessed liquid wastes from the low level drains tanks [LW-TK-3A/B]. It did not remove any standard ODCM Controls specified in NUREG-1301. 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.
8.2.35 Change {35) ofBV-1 and 2 ODCM {Effective March 2013) 8.2.35.1 A description of the changes implemented with this revision are as follows:
8.2.35.1.1 8.2.35.1.2 Procedure l/2-0DC-1.01, Rev 17: Removed reference Tables 1.2-la and 1.2-lb that were deleted from l/2-0DC-2.01 (previous Attachment B) in revision 9.
Procedure l/2-0DC-2.01, Rev 13: This change added descriptions of the Ul Chemical Waste Sump and U2 Cable Vault Sump discharge points. ODCM controls are now officially established for these sumps, including two volume recirculation and batch sampling requirements.
8.2.35.2 The justifications used for change (35) of the ODCM are as follows:
8.2.35.2.1 Procedure 1/2-0DC-1.01, Rev 17: This change removed a reference from the document that was overlooked in a previous revision. It did not remove any standard ODCM Controls specified in NUREG-1301.
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.
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75ofl14 8.2.35.2.2 Procedure l/2-0DC-2.01, Rev 13: This change added descriptions of discharge points and employed ODCM controls where not previously implemented This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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.
8.2.36 Change (36) ofBV-1 and 2 ODCM (Effective March 2014) 8.2.36.1 A description of the changes implemented with this revision are as follows:
8.2.36.1.1 8.2.36.1.2 8.2.36.1.3 Procedure l/2-0DC-2.01. Rev 14: This change added descriptions of the new Unit 1 Liquid Radwaste System components that were installed via ECP 12-0478. New components that were installed include Liquid Waste Pre-Conditioning Filter, Liquid Waste Demineralizer, Rad Waste Reverse Osmosis (RWRO) Pre-filter, RWRO Skid, Polishing Vessel, Antimony Vessel and Sample Sinks.
Procedure 1/2-0DC~2.02. Rev 4: This change added dose equations and dose factors for carbon-14 per notification 600737534 and dose factors for antimony-126 per notification 600727275 (from CR#2012-17177).
Procedure 1/2-ODC-2.03. Rey 5: This change removed Searight's Dairy farm from milk sample locations (Notification 6008201182 and CR#2013-03554) 8.2.36.2 The justifications used for change (36) of the ODCM are as follows:
8.2.36.2.1 8.2.36.2.2 Procedure l/2-0DC-2.01. Rev 14: The current Unit 1 Liquid Waste system has been removed and replaced with new components. This change documents and describes the new liquid waste components.
This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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.
Procedure l/2-0DC-2.02. Rev 4: This change added the ability to perform dose calculations for more isotopes. Carbon-14 does not currently have a regulatory limit for discharge, but is required to be reported. This revision did not remove any standard ODCM Controls specified in NUREG-1301, Therefore, this change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFRPart 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50.
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76 of114 8.2.36.2.3 Procedure 1/2-ODC-2.03, Rev 5: This change removed Searight's Dairy farm from milk sample locations. The local farmer notified Beaver Valley that the dairy would be closing permanently, the dairy cattle would be sold and the property will be utilized for hay bailing and possibly beef cattle. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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.
8.2.37 Change (37) ofBV-1 and 2 ODCM (Effective October 2014) 8.2.37.1 A description of the changes implemented with this revision are as follows:
8.2.37.1.1 8.2.37.1.2 8.2.37.1.3 8.2.37.1.4 8.2.37.1.5 Procedure l/2-ODC-1.01, Rev 20: This change added 10 CFR 72.104 to the reference and acceptance criteria per ECP 12-0250. The change also documents changes to 1/2-ODC-2.02 RS, 1/2-ODC-2.03 R6, 1/2-ODC-2.04 R2, and 1/2-ODC-3.03 Rl2.
Procedure l/2-0DC-2.02, Rev 5: This change added the definition for "1.1" in equation 2.1(2)-18 per notification 600877226 and added 10 CFR 72.104 to the reference and acceptance criteria per ECP 12-0250.
Procedure l/2-0DC-2.03. Rev 6: This change added 10 CFR 72.104 to the reference and acceptance criteria per ECP 12-0250.
Procedure l/2-ODC-2.04. Rev 2: This change added 10 CFR 72.104 to the reference and acceptance criteria per ECP 12-0250.
Procedure l/2-0DC-3.03. Rev 12: This change added 10 CFR 72.104 to the reference and acceptance criteria and noted ISFSI dose considerations are included in dose calculations per ECP 12-0250.
8.2.37.2 The justifications used for change (37) of the ODCM are as follows:
8.2.37.2.1 Procedure l/2-0DC-1.01, Rev 20: This change added 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS, to the reference and acceptance criteria per ECP 12-0250, Independent Spent Fuel Storage Installation (ISFSI) Spent Fuel Storage System (SPSS) System Incorporation. With the installation of the SPSS additional consideration must be given when updating the ODCM. 10 CFR 72.104 document the requirements. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
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, 10 CFR 72.104 and Appendix I to 10 CFR 50.
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77 nf 114 8.2.37.2.2 Procedure l/2-0DC-2.02, Rev 5: This change added a definition for equation 2.1(2)-18 to provide user clarification and ensure equation formatting is consistent throughout the procedure. This change also added 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS, to the reference and acceptance criteria per ECP 12-0250, Independent Spent Fuel Storage Installation (ISFSI) Spent Fuel Storage System (SFSS) System Incorporation. With the installation of the SFSS additional consideration must be given when updating the ODCM. 10 CFR 72.104 document the requirements. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.l 04 and Appendix I to 10 CFR 50.
8.2.37.2.3 Procedure l/2-0DC-2.03, Rev 6: This change added 10 CFR 72.104, Criteria for radioactive materials in eftluents and direct radiation from an ISFSI or MRS, to the reference and acceptance criteria per ECP 12-0250, Independent Spent Fuel Storage Installation (ISFSI) Spent Fuel Storage System (SFSS) System Incorporation. With the installation of the SFSS additional consideration must be given when updating the ODCM. 10 CFR 72.104 document the requirements. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
Therefore, this change will maintain the level of radioactive eftluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.37.2.4 Procedure l/2-0DC-2.04, Rev 2: This change added 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS, to the reference and acceptance criteria per ECP 12-0250, Independent Spent Fuel Storage Installation (ISFSI) Spent Fuel Storage System (SFSS) System Incorporation. With the installation of the SFSS additional consideration must be given when updating the ODCM. 10 CFR 72.104 document the requirements. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
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, 10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.37.2.5 Procedure l/2-0DC-3.03. Rev 12: This change added 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS, to the reference and acceptance criteria per ECP 12-0250, Independent Spent Fuel Storage Installation (ISFSI) Spent Fuel Storage System (SFSS) System Incorporation. With the installation of the SFSS additional consideration must be given when updating the ODCM. 10 CFR 72.104 document the requirements. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
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78 of 11A.
Therefore, this change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36~
10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.38 Change (38) ofBV-1 and 2 ODCM {Effective February 2015) 8.2.38.1 A description of the changes implemented with this revision are as follows:
8.2.38.1.1 8.2.38.1.2 8.2.38.1.3 8.2.38.1.4 Procedure l/2-0DC-2.01, Rev 15: This change added clarification to section 8.3.1 describing when the factor of 3 can be used, removed the OECi value for Ba-137m and replaced the reference (5) with"-" for OECi value for Br-85 and Rh-106 from Attachment A, Table 1.1-1 a and Table 1.1-1 b as noted in notification 60092820 I.
Procedure l/2-0DC-2.02, Rev 6: This change removed all references, efficiencies and setpoints for the Eberline SPING Radiation Monitors and replaced references, efficiencies and setpoints for the Mirion PING Radiation Monitors. These changes reflect the radiation monitor replacement at Unit 1 per ECP-10-0150, Replacement ofBVl Effluent Radiation Monitoring System Components. The height of the process vent release point was also corrected to align with the USF AR, as noted in notification 600877226.
Procedure l/2-0DC-3.02, Rev 3: This change replaced the reference to 10 CFR Part 20.106(b) with 10 CFR Part 20.1301. The reference itself has not changed, only the location, as noted in notification 600877226.
Procedure l/2-0DC-3.03, Rev 13: This change removed all references and setpoints for the Eberline SPING Radiation Monitors and replaced references and setpoints for the Mirion PING Radiation Monitors.
These changes reflect the radiation monitor replacement at Unit 1 per ECP-10-0150, Replacement of BVl Effluent Radiation Monitoring System Components.
8.2.38.2 The justifications used for change (38) of the ODCM are as follows:
8.2.38.2.1 Procedure l/2-0DC-2.01, Rev 15: This change added clarification for mixing factors and corrected values for Ba-137m in Attachment A to match 10 CFR 20. Also the reference (5) for Br-85 and Rh-106 OECi values were changed to a"-" because 10 CFR 20 does not list a value.
This revision did not remove any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36~ 10 CFR 72.104 and Appendix I to 10 CFR 50.
Beaver Valley Power Station
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79 nf 114 8.2.38.2.2 Procedure l/2-0DC-2.02, Rev 6: The references, efficiencies, and setpoints for the Eberline SPING Radiation monitors were removed to support ECP 10-0150 which installs new Mirion PING Radiation Monitors. The setpoints for the new Mirion Monitors were determined and approved in calculation package ERS-HHM-87-014, Unit I/ Unit 2 ODCM Gaseous Effluent Monitor Setpoints and the efficiencies were determined and approved in calculation package ERS-SFL-85-031, Gaseous Effluent Monitor Efficiency Data. The height of the process vent was also revised to align with the UFSAR. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
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, 10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.38.2.3 Procedure l/2-0DC-3.02, Rev 3: This change only updated the reference for 10 CFR Part 20. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.38.2.4 Procedure l/2-0DC-3.03, Rev 13: The references and setpoints for the Eberline SPING Radiation monitors were removed to support ECP 10-0150 which installs new Mirion PING Radiation Monitors. The setpoints for the new Mirion Monitors were determined and approved in calculation package ERS-HHM-87-014, Unit I/ Unit 2 ODCM Gaseous Effluent Monitor Setpoints. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104 and Appendix I to 10 CFR 50.
8.2.39 Change (39) ofBV-1 and 2 ODCM (Effective March 2016) 8.2.39.1 A description of the changes implemented with this revision are as follows:
8.2.39.1.1 Procedure l/2-0DC-2.01. Rev 16: This change added dose factors for beryllium-7 (Be-7), selenium-75 (Se-75), tin-113 (Sn-113 ), tin-117m (Sn-117), and antimony-122 (Sb-122) per CR-2015-15885. Minor additions were included throughout to where ERS-ATL-83-027 is to be referenced. Table 1.3-1 was updated to include ingestion dose commitment factors.
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RO of 114 8.2.39.1.2 Procedure l/2-0DC-2.02, Rev 7: This change revised selenium-75 dose factors. ABS consulting provided original dose factor values and ERS-LMR.-15-006 improved them. ERS-ATL-83-027 was updated with the new values. Minor additions were included throughout to where ERS-ATL-89-014 is to be referenced. Table 2.2-13 was updated for organ dose parameters and Tables 2.3-2 through 2.3-20 were updated for P&I organ dose factors.
8.2.39.2 The justifications used for change (39) of the ODCM are as follows:
8.2.39.2.1 8.2.39.2.2 Procedure l/2-0DC-2.01, Rev 16: This change improved the ability to perform dose calculations for selenium-75. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-2.02, Rev 7: This change added the ability to perform dose calculations for more isotopes. Selenium-75 dose factors are more accurate. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Beaver Valley Power Station
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81 of 114 8.2.40 Change (40) ofBV-1 and 2 ODCM (Effective November 2016) 8.2.40.1 A description of the changes implemented with this revision are as follows:
8.2.40.1.1 8.2.40.1.2 8.2.40.1.3 8.2.40.1.4 Procedure 1/2-0DC-l.0l, Rev 23: The revision updates ATTACHMENT C for PING monitors.
Procedure l/2-ODC-2.02, Rev 8: The revision was implembnted because ofECP-16-0026 to change the sample pump on the RM-lVS-lOlB skid. This altered the efficiencies that changed the alarm setpoints for RM-lVS-lOlB. The primary and alternate radiation monitors for Unit 1 Auxiliary Building Vent and Containment/SLCRS Vent. The PING monitors are now the primary monitors for these release points. Minor grammar corrections.
\\
Procedure l/2-0DC-2.03. Rev 7: The revision updates maps for REMP samples. Minor changes to table data for consistency with other tables.
Procedure l/2-0DC-3.03, Rev 14: This revision updates the primary and alternate radiation monitors for Unit 1 Auxiliary Building Vent and Containment/SLCRS Vent. The PING monitors are now the primary monitors for these release points. The Preplanned Method of Monitoring for Unit 1 and 2 form was revised to from HPP form to ENVform.
8.2.40.2 The justifications used for change (40) of the ODCM are as follows:
8.2.40.2.1 Procedure l/2-0DC-1.01, Rev 23: This change was to be concurrent with 1/2-ODC-2.02. The PING monitors were installed, but not change
, over to being the primary monitors for Unit 1 Auxiliary Building Vent and Containment/SLCRS Vent This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appen~ I to 10 CFR 50.
8.2.40.2.2 Procedure l/2-ODC-2.02, Rev 8: This change was in support of ECP-16-0026. The efficiencies for RM-IVS-lOlB were determined and approved in calculation package ERS-HHM-87-014, Unit 1/ Unit 2 ODCM Gaseous Effluent Monitor Setpoints and the efficiencies were determined and approved in calculation package ERS-SFL-85-031, Gaseous Eflluent Monitor Efficiency Data. The PING monitors were installed, but not designated as the primary monitors for Unit 1 Auxiliary Building Vent and Containment/SLCRS Vent. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
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~') of 114 8.2.40.2.3 8.2.40.2.4 Procedure l/2-0DC-2.03, Rev 7: This change was in accordance with CR-2016-10379 to update the REMP sample location maps. This revision did not remove any standard ODCM Controls specified in NUREG-1301. Therefore, this change will maintain the level of radioactive eflluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-3.03, Rev 14: This change was to be concurrent with 1/2-ODC-2.02. The PING monitors were installed, but not designated as the primary monitors for Unit 1 Auxiliary Building Vent and Containment/SLCRS Vent Notification 601054826 was generated to revise an error on form 1/2-HPP-4.02.009.F0l. During the revision, the process provided by the HPP form was to be improved upon, which led it being integrated into form 1/2-ENV-05.05.F07. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
Therefore, this change will maintain the level of radioactive eflluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
8.2.41 Change (41) ofBV-1 and 2 ODCM (Effective January 2017) 8.2.41.1 A description of the changes implemented with this revision are as follows:
8.2.41.1.1 Procedure l/2-0DC-2.03, Rev 8: This revision updates the waterborne surface sample location from #2.1 to #5 (Notification #601018638, task 10). Milk sample location #114, Covert residence, was added to Table 3.0-1 and the table corresponding to Figure 3.0-4. Maps for these locations were updated with changes.
8.2.41.2 The justifications used for change (41) of the ODCM are as follows:
8.2.41.2.1 Procedure l/2-ODC-2.03, Rev 8: This change was implemented because waterborne surface sample location #2.1, Midland-AT!
Allegheny Ludlum, has become inaccessible due to facility closure.
The sample location is a current location for waterborne surface sampling, but will now considered a required sample location. The Covert residence milk sample location was added due to ability to complete routine samples in the last three years. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
Therefore, this change will maintain the level of radioactive eflluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
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8.2.42 Change {42) ofBV-1 and 2 ODCM {Effective January 2018) 8.2.42.l A description of the changes implemented with this revision are as follows:
8.2.42.1.1 8.2.42.1.2 8.2.42.1.3 Procedure l/2-0DC-1.01. Rev 25: This revision updated dates for changes to the ODCM, changing January 2015 to February 2015 (Change 38) and changing February 2016 to March 2016 (Change 39).
Procedure l/2-0DC-2.01, Rev 17: This revision updates BV-1 Liquid Monitor Setpoints table with new setpoints for RM-lLW-104, RM-lLW-116, and RM-lRW-101 and Table 1.1-la with new detection efficiencies. The change to RM-lRW-101 was due to a typo in the calculation package. Other changes include reference reorganization, minor formatting and grammar fixes.
Procedure l/2-0DC-2.03, Rev 9: This revision modified Table 3.0-1 to make text visible in table row.
8.2.42.2 The justifications used for change ( 42) of the ODCM are as follows:
8.2.42.2.1 8.2.42.2.2 8.2.42.2.3 Procedure l/2-0DC-1.01, Rev 25: This change was implemented because of SA-BN-2017-0826, and Notification 601136559 was generated to make these changes. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-2.01, Rev 17: The change was implemented because of ECP-16-0113 that upgraded from Model 843-30 detector to Model 953-36E detector for both RM-lLW-104 and RM-lLW-116.
The efficiencies were approved in calculation package ERS-SFL 039, Isotopic Efficiencies for Unit 1 Liquid Process Monitors and the setpoints were determined and approved in calculation package ERS-ATL-93-021, Process Alarm Setpoints for Liquid Effluent Monitors.
This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Procedure l/2-ODC-2.03. Rev 9 This change was implemented because ofSA-BN-2017-0826, and Notification 601136559 was generated to make these changes. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
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RA. of 114 8.2.43 Change (43) ofBV-1 and 2 ODCM (Effective August 2018) 8.2.43.1 A description of the changes implemented with this revision are as follows:
8.2.43.1.1 8.2.43.1.2 8.2.43.1.3 Procedure l/2-0DC-1.01, Rev 26: This revision reflects the changes made to l/2-0DC-2.02 and l/2-ODC-3.03 regarding Unit I effluent monitors and the alternative particulate and iodine sample location changes.
Procedure l/2-0DC-2.02, Rev 9: This revision applies the new efficiencies and setpoints to RM-IVS-107B. Equation [2.1(1)-3] was missing from aside equation and math typo was corrected for Unit 2 batch release discharge flow for containment purge.
Procedure l/2-0DC-3.03, Rev 15: This revision updated Unit I effluent monitor alternative particulate and iodine sample locations. National Bureau of Standards was updated to National Institute of Science and Technology. REMP LLDs were taken out of scientific notation to match tables. Minor table formatting and grammar corrected.
8.2.43.2 The justifications used for change (43) of the ODCM are as follows:
8.2.43.2.l 8.2.43.2.2 Procedure l/2-0DC-1.01, Rev 26: This change was implemented because ofCR-2017-04211, 2018-02456 and ECP-17-0112. This revision did not remove any standard ODCM Controls specified in NUREG-130 I. Therefore, this change will maintain the level of radioactive effluent control required by IO CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-2.02, Rev 9: This change was implemented because ofECP-16-0113 that upgrades RM-IVS-107B\\from a Model 843-30 detector to a Model 953-25TE detector. The efficiencies were approved in calculation package ERS-SFL-85-031, Unit 1 Gaseous Monitor Efficiency Data and the setpoints were determined and approved in calculation package ERS-HHM-87-014, Unit I/ Unit 2 ODCM Gaseous Effluent Monitor Setpoints. This revision did not remove any standard ODCM Controls specified in NUREG-1301.
Therefore, this change will maintain the level of radioactive effluent control required by IO CFR 20.1302, 40 CFR Part 190, IO CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
Beaver Valley Power Station
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R5 of 114 8.2.43.2.3 Procedure l/2-0DC-3.03, Rev 15: This change was implemented because of CR-2017-04211, 2018-02456 and ECP-17-0112. These listed documents relate to the station's lack of representative sampling, with respect to isokinetic sampling. CR-2017-04211 was the initial discovery of the issue and initial plan to correct it CR-2018-02456 was to document the preliminary NRC Green Non-cited Violation are non-representative sampling and resolution to the problem. ECP-17-0112 is the retirement package for tu.ming on the RAS pumps at the SA 9/10 locations. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR50.
8.2.44 Change (44) ofBV-1 and 2 ODCM (Effective April 2019) 8.2.44.1 A description of the changes implemented with this revision are as follows:
8.2.44.1.1 8.2.44.1.2 8.2.44.1.3 Procedure l/2-0DC-1.01, Rev 27: This revision reflects the change in ECPs, from ECP-17-0112 to ECP-17-0378 regarding the SA 9/10 radiation monitor retirement Procedure l/2-0DC-2.02, Rev 10: This revision applies the new efficiencies and setpoints to RM-lVS-lOlB.
Procedure l/2-0DC-3.03, Rev 16: This revision updates Attachment D for both Unit 1 and Unit 2 radiation monitor with respect their channel operational tests.
8.2.44.2 The justifications used for change (44) of the ODCM are as follows:
8.2.44.2.1 Procedure l/2-ODC-1.01, Rev 27: This change was implemented because of ATA-2019-0132 to correct the number of the ECP associated with the modifications. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR72.104, and Appendix I to 10 CFR 50.
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SU, of' 114 8.2.44.2.2 8.2.44.2.3 Procedure l/2-ODC-2.02, Rev 10: This change was implemented because ofECP-18-0043 that upgrades RM-1VS-101B from a Model 843-30 detector to a Model 953-25TE detector. The efficiencies were approved in calculation package ERS-SFL-85-031, Unit 1 Gaseous Monitor Efficiency Data and the setpoints were determined and approved in calculation package ERS-HHM-87-014, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints. Typo corrections were made on page 53 for display of the X/Q variables on those lines. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR50.
Procedure l/2-0DC-3.03, Rev 16: This change was implemented because of ATA-2019-0132 & 3863. The ATA ending in 3863 address the changes in Attachment D for Channel Operational Testing. This test was moved from 31 days to 92 days to support the station and reducing wear on the radiation monitors. This revision did not remove any standard ODCM Controls specified in NUREG-1301. 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, 10 CFR 72.104, and Appendix I to 10 CFR 50.
8.2.45 Change {45) ofBV-1 and 2 ODCM (Effective July 2019) 8.2.45.1 A description of the changes implemented with this revision are as follows:
8.2.45.1.1 8.2.45.1.2 Procedure l/2-0DC-1.01, Rev 28: This revision made a minor correction to the description of change 44 and reflects the changes made to l/2-ODC-2.02 and l/2-0DC-3.03 regarding Unit 2 Condensate Polishing Building retirement activities. Controls removed from Attachment C Table F: 3b. Two form references corrected for previously voided forms.
Procedure l/2-0DC-2.02, Rev 11: This revision removes Condensate Polishing (CB-2) as a significant effluent pathway, removes continuous surveillance requirements (sampling and monitoring) for this pathway and 2HVS-RQ112 and therefore treats all references to CB-2 the same as TV-2 (Turbine Building Vent). A correction was made to the variables (X/Q)v in equations [2.2-1] and [2.2-2] because it should reference ground releases, not elevated. The turbine building variable was added to equation [2.3-7] and [2.3-8] because it was missing. A clarifying statement was added for carbon-14 dose methodology.
.J Beaver Valley Power Station
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R7 of 114 8.2.45.1.3 Procedure l/2-0DC-3.03, Rev 17: This revision removes Condensate Polishing (CB-2) as a significant effluent pathway, removes continuous surveillance requirements (sampling and monitoring) for this pathway and 2HVS-RQ112 and therefore treats all references to CB-2 the same as TV-2 (Turbine Building Vent). Additionally, references to RAS Pumps and associated flow rate devices were changed to generic portable sampling equipment.
8.2.45.2 The justifications used for change ( 45) of the ODCM are as follows:
8.2.45.2.1 8.2.45.2.2 8.2.45.2.3 Procedure l/2-0DC-1.01, Rev 28: This change was implemented to document removal of ODCM requirements based on the elimination of the source term associated with the retirement of the Condensate Polishing System via ECP 13-0829. Minor typo in change description 44 was corrected. This change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-2.02, Rev. 11 :' This change was implemented to remove Condensate Polishing as a significant eflluent pathway at Unit
- 2. Removal of ODCM requirements is acceptable based on the e1imination of the source term associated with the retirement of the Condensate Polishing System via ECP 13-0829. A correction was made to the definition of a variable and the turbine building variable was added to equation [2.3-7] and [2.3-8]. Editorial clarification about carbon-14 dose equations to allow use of the industry accepted EPRI methodology is an improvement to the program. 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, 10 CFR72.104, and Appendix I to 10 CFR 50.
Procedure l/2-0DC-3.03, Rev 17: This change was implemented to remove Condensate Polishing as a significant effluent pathway at Unit
- 2. Removal of ODCM requirements is acceptable based on the e1imination of the source term associated with the retirement of the Condensate Polishing System via ECP 13-0829. Additionally, references to RAS Pumps and associated flow rate devices were changed to generic sampling equipment. This change will maintain the level of radioactive eflluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR72.104, and Appendix I to 10 CFR.50.
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RRnf114 8.2.46 Change (46) ofBV-1 and 2 ODCM {Effective April 2020) 8.2.46.1 A description of the changes implemented with this revision are as follows:
8.2.46.1.1 8.2.46.1.2 8.2.46.1.3 Procedure 1/2-ODC-l.O 1, Rev 29: This revision reflects the changes made to l/2-ODC-2.01 and l/2-ODC-3.03 regarding ECP 19-0230 which removes the effluent flow path to the river and abandons radiation monitor RM-lDA-100. Controls removed from Attachment C Table F: 2a.
Procedure l/2-0DC-2.01, Rev 18: This revision removes the setpoints and refences for RM-lDA-100 based on the removal of the effluent flow path to the river monitored by RM-lDA-100 and abandonment of radiation monitor RM-lDA-100 per ECP 19-0230.
Procedure l/2-0DC-3.03, Rev 18: This revision removes surveillance requirements for the Auxiliary Feed Pump Bay Drain Monitor [RM-lDA-100]. This change is based on ECP 19-0230 which removes the effluent pathway to the river and abandons RM-lDA-100.
8.2.46.2 The justifications used for change (46) of the ODCM are as follows:
8.2.46.2.1 8.2.46.2.2 8.2.46.2.3 Procedure 1/2-0DC-l.O 1, Rev 29: This change was implemented to document removal of ODCM requirements based on the elimination of effluent path way to the river for the Unit 1 Auxiliary Feed Pump Bay and the abandonment ofRM-lDA-100 via ECP 19-0230.
This change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR72.104, and Appendix I to 10 CFR 50.
Procedure l/2-ODC-2.01, Rev. 18: This change was implemented to document removal of ODCM requirements based on the elimination of effluent pathway to the river for the Unit 1 Auxiliary Feed Pump Bay and the abandonment ofRM-lDA-100 via ECP 19-0230. Removal of ODCM requirements are acceptable based on the removal of the effluent pathway. 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, 10 CFR72.104, and Appendix I to 10 CFR 50.
Procedure l/2-ODC-3.03, Rev 18: This change was implemented to document removal of ODCM requirements based on the elimination of effluent pathway to the river for the Unit 1 Auxiliary Feed Pump Bay and the abandonment ofRM-lDA-100 via ECP 19-0230. Removal of ODCM requirements are acceptable based on the removal of the effluent pathway. This change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104, and Appendix I to 10 CFR 50.
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Beaver Valley Power Station Titlo:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT A Page 1 of6 LIST OF ODCM TABLES LIQUID EFFLUENTS Included in Procedure l/2-0DC-2.01 1.1-la BV-1 Liquid Source Term 1.1-lb BV-2 Liquid Source Term 1.3-1 Ai-c Values For An Adult For The Beaver Valley Site GASEOUS EFFLUENTS Included in Procedure l/2-ODC-2.02 2.1-la BV-1 Radionuclide Mix For Gaseous Effluents 2.1-lb BV-2 Radionuclide Mix For Gaseous Effluents 2.1-2a BV-1 Monitor Detector Efficiencies
- 2. l-2b BV-2 Monitor Detector Efficiencies Procedure Number:
l/2-0DC-1.01 Unit 1/2 Revision:
29 Level OfUao:
General Skill Reference Page Number:
R9 of 114 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 rJ0 Included in Procedure l/2-0DC-2.02 2.2-4 2.2-5 2.2-6 2.2-7 2.2-8 2.2-9 2.2-10 BV-1 And 2 Containment Vents (Ground Release)
BV-1 And 2 Ventilation Vents (Ground Release)
BV-1 And 2 Process Vent (Elevated Release)
BV-1 And 2 Turbine Building Vents (Ground Release)
BV-2 Decontamination Building Vent (Ground Release)
BV-2 Waste Gas Storage Vault Vent (Ground Release)
BV-2 Condensate Polishing Building (Ground Release)
Beaver Valley Power Station
Title:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT A Page 2 of6 LIST OF ODCM TABLES Procedure Number:
112-0DC-l.01 Unit 1/2 Revision:
2g Level Of Use:
General Skill Reference Page Number:
90 nf'l 14 NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS Included in l/2-0DC-2.02 2.2-11 2.2-12 Dose Factors For Noble Gases And Daughters Dose Parameters For Finite Elevated Plumes, Beaver Valley Site P&I DOSE PARAMETERS Included in l/2-0DC-2.02 2.2-13 Pi't Values For A Child For The Beaver Valley Site MODES OF GASEOUS RELEASES Included in Procedure l/2-0DC-2.02 23-1 Modes Of Gaseous Release From The Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50 P&I ORGAN DOSE FACTORS Included in l/2-0DC-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 RV alues for Meat - Child 2.3-13 R Values for Cow Milk - Adult 2.3-14 R Values for Cow Milk - Teen 2.3-15 R Values for Cow Milk - Child 2.3-16 R Values for Cow Milk - Infant
\\.
f Beaver Valley Power Station Trtle:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT A Page 3 of 6 LIST OF ODCM TABLES 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 Procedorc Number:
l/2-0DC-1.01 Unit 1/2 Revision:
?.Q Level OfUae:
General Skill Reference Page Number:
91 nf 114 CONTINUOUS RELEASE DEPOSIDON PARAMETERS (0-5 Miles)TrdudooinPiocedureJ.a..ODC-202 23-21 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 DEPOSIDON PARAMETERS (SPECIAL DISTANCES) Included in Procedure l/2-0DC-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)
BATCH RELEASE DISPERSION PARAMETERS {Special Distances) Included in Procedure l/2-ODC-2.02 2.3-35 BV-1 And 2 Containment Vents (Ground Release) 2.3-36 BV-1 And 2 Ventilation Vents (Ground Release)
Beaver Valley Power Station Proccdore Number:
l/2-ODC-1.01
Title:
ODCM: Index, Matrix and History ofODCM Changes 2.3-37 A ITACIIMENT A Page 4 of6 LIST OF ODCM TABLES BV-1 And 2 Process Vent (Elevated Release)
Unit 1/2 R.cviaion:
?Q Level OfUsc:
General Skill Reference
~Number:
Q? nf 114 BATCH RELEASE DISPERSION PARAMETERS (0-5 Miles) Included in Procedure l/2-ODC-2.02 2.3-38 BV-1 And 2 Process Vent (Elevated Release)
ENVIRONMENTAL MONITORING Included in Procedure l/2-0DC-2.03 3.0-1 Radiological Environmental Monitoring Program DISPERSION CALCULATION Included in Procedure 1/2-ODC-3.01 A:1 BV-1 And2 Release Conditions INPUTS TO COMPUTER CODES Included in Procedure l/2-0DC-3.01 B:la Inputs To GALE Code For Generation OfBV-1 Liquid Source Term Mixes B:lb Inputs To SWEC LIQlBB Code For Generation OfBV-2 Liquid Source Term Mixes
-B:2a Inputs To SWEC GASlBB Code For Generation OfBV-1 Gaseous Source Term Mixes B:2b Inputs To SWEC GASlBB Code For Generation ofBV-2 Gaseous Source Term Mixes ODCM CONTROLS Included in Procedure l/2-0DC-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 Requirements C:3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation 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
\\
Beaver Valley Power Station Procedure Number:
l/2-0DC-1.01 ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT A Page 5 of6 LIST OF ODCM TABLES C:3.12-1 Radiological Environmental Monitoring Program Unit:
1/2 Level Of Use:
General Skill Reference Page Number:
Q~ nf 114 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 l/2-0DC-3.03 E:6.9-1 Environmental Radiological Monitoring Program Summary ODCM CONTROLS PROCEDURE MATRIX Included in Procedure l/2-ODC-1.01 F:la BV-1 Radiation Monitoring Instrumentation Surveillance F: 1 b BV-2 Radiation Monitoring Instrumentation Surveillance F:2a BV-1 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-1 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-1 and 2 Gaseous Effluent Treatment Surveillances F: 12a BV-1 Gaseous Storage Tank Activity Limit Surveillances F: 12a BV-2 Gaseous Storage Tank Activity Limit Surveillances F: 13 BV-1 and 2 Total Dose Surveillances
I Beaver Valley Power Station Procedure Number.
l/2-0DC-1.01
Title:
Unit Level OfUse:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number:
?Q QA. of 11A.
ATTACHMENT A Page 6 of 6 LIST OF ODCM TABLES F:14 BV-1 and 2 REMP Surveillances F:15 BV-1 and 2 Land Use Census Surveillances F:16 BV-1 and 2 Interlaboratory Comparison Program
Beaver Valley Power Station
Title:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT B Page 1 of 1 LIST OF ODCM FIGURES LIQUID EFFLUENTS Included in Procedure l/2-0DC-2.01 1.4-1 BV-1 Liquid Radwaste System 1.4-2 BV-2 Liquid Radwaste System 1.4-3 BV -1 and 2 Liquid Effluent Release Points 5-1 Site Boundary For Liquid Eflluents GASEOUS EFFLUENTS Included in Procedure l/2-0DC-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 Eflluents Proccdorc Number.
l/2-0DC-1.01 Unit Level Of Use:
1 /2 General Skill Reference Revision:
Page Number.
?.Q 95 nf114 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Included in Procedure l/2-0DC-2.03 3.0-1 Air Sampling Locations 3.0-2 TLD Locations 3.0-3 Shoreline Sediment, Surface Water, And Drinking Water Sampling Locations 3.0-4 Milk Sampling Locations 3.0-5 Foodcrop Sampling Locations 3.0-6 Fish Sampling Locations
Beaver Valley Power Station Procedure Number:
l/2-0DC-1.01
Title:
Unit Level OfUsc:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number:
TABLE F: 1a ATTACHMENT C Page 1 of 19 ODCM CONTROLS PROCEDURE MA TRIX BV-1 RADIATION MONITORING INSTRUMENTION SURVEILLANCES 1/2-0DC-3.03, Attachment D Control 3.3.3,1: Maintain Radiation Monitoring Channels In Table 3.3-6 OPERABLE APPLICABILITY: MODES 1 thru 4 ODCMSR DESCRIPTION PROCEDURE 4.3.3.1 Test Monitors at Table 4.3-3 Fl'8QU80CY 4.3.3.1.1 Noble Gas Effluent MonHors -
NOTE: Actions for INOPERABLE Monitors are-PINGS documented In the Ooaratlons & Rad Effluent Shift Loos.
4.3.3.1.1.a Supplementary Leak Collection 1 MSP-43.59-I: Channel Calibration and Release System Fonn 1/2-ADM-1611.F03: Channel Check (RM-1VS-110 HRNG Rel & LRNG 1OST-43.7: Channel Operational Test Rel) 4.3.3.1.1.b Auxlfiary Building Ventilation 1 MSP-43.60-I: Channel Calibration System (RM-1VS-109 HRNG Rel &
Fonn 1/2-ADM-1611.F03: Channel Check LRNG Re0 1 OST-43.07: Channel Ooeratlonal Test 4.3.3.1.1.c Process Vent System (RM-1 GW-1 MSP-43.68-I: Channel Calibration 109 HRNG Rel & LRNG)
Fonn 1/2-ADM-1611.F03: Channel Check 1 OST -43. 7: Channel Ooeratlonal Test 4.3.3.1.2 Noble Gas Steam Effluent NOTE: Actions for INOPERABLE Monitors are Monitors documented In the Ooeratlona & Rad Effluent Shift Loas.
4.3.3.12.clv.1.2a Atmospheric Steam Dump Valve 1MSP-43.62-I: RM-1MS-100A Channel CaBbration ano Code Safety Valve Discharge 1 MSP-43.63-1: RM-1MS-1008 Channel CaUbration (RM-1MS-100A, B, C) 1MSP-43.64-I: RM-1MS-100C Channel CaUbratlon Fonn 1/2-ADM-1611.F03: Channel Check 10ST-43.5: Channel Ooeratlonal Test 4.3.3.12.b Auxiliary Feedwater Pump 1 MSP-43.65-I: Channel Callbration Turbine Exhaust (RM-1MS-101)
Form 1/2-AOM-1611.F03: Channel Check 10ST-43.5: Channel Operational Test
Beaver Valley Power Station Proccdore Number:
l/2-0DC-1.01
Title:
Unit Level OfU110:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number:
29 114 of 114 AITACIIMENT C Page 19 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 REMP PROGRAM SURVEILLANCES TABLE F: 14 1/2-0DC:3,03. Attachment Q Control 3.12.1: Radlologlcal Environmental Monitoring Program (REMP}
APeLIQABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.12.1.1 Using Locations In the ODCM -Collect 1/2-ENV-02.01: Radiological Environmental Monitoring Program and Analyze Samples per Tables 3.12-1/2-ENV-03.01: Environmental Sampling 1 3.12-2 & 4.12-1 TABLE F: 15 1[2-0DC-3.Q3, Attachment R Control 3,12,i: Land Use Census APPL!CtiBl!.llY: At All nmes ODCM DESCRIPTION PROCEDURE SR 4.12.2.1 Using the Best AvallabJe Method -
1/2-ENV-02.01: Radlologlcal Environmental Monitoring Program Conduct a Land Use Census Yearly 1/2-ENV-04.02: REMP Calculations Between 6/1 & 10/1 TABLE F: 16 1/2-0QC-3.Q3. Attachment ~ Coatrol 3.12,3: lnterlaboratory Comparison Program APeLICABILITY: At All Times ODCM DESCRIPTION PROCEDURE SR 4.12.3.1 Include Analysis Results of the 1/2-ENV-02.01: Radiological Environmental Monitoring Program lnte,rlaboratory Comparison Program Spilt Sample Program with PA-DEP in the Annual Radlologlcal Spike Sample Program with Independent Laboratory Environmental Reoort 1/2-ENV-01.05: Section 4 of AREOR Template
Beaver Valley Power Station
Title:
Proccdurc Number:
l/2-0DC-1.01 Unit 1/2 Level OfUse:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
JQ Page Number:
1 B nf 114 ATTACHMENT C Page 18 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 TOTAL DOSE SURVEILLANCES TABLE F: 13 1/2-0DC-3,03, Attachment P Control 3.11.4, 1: Liquid And Gaseous Doses APPLICABILITY: Ai All Times ODCM SR 4.11.4.
1.1 DESCRIPTION
Using the ODCM - Detennlne Cumulative Gas & Liquid Dose per Control 3.11.1.2, 3.11.2.2, 3.11.2.3 PROCEDURE Fonn 1/2-ENV--01.05.F01: Annual RETS Report (40CFR190)
Fonn 1/2-ENV-05.04.F01: RWDA-L Fonn 1/2-ENV--05.05.F01: RWDA-G Fonn 1/2-ENV--01.03.F01: Continuous Release Pennlt Form 1/2-HPP-3.06.012.F01: Abnonnal Gaseous Releases 1/2-ENV-01.04: Effluent Data Loos (40CFR190)
Beaver Valley Power Station
Title:
Procedure Number:
l/2-ODC-1.01 Level OfUac:
f Unit 1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes
~on:
,()
Page Number:
ATTACHMENT C Page 17 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVBLLANCES TABLE F: 12a 11 ?. of 114 1/2-0DC-3.03. Attachment O Control 3.11.2.5: Maintain Gas Storage Tank Activity within the following Hmlts:
1GW-TK:1A: ~52000 Curles Noble Gas (Considered Xe-133) 1GW-TK-1B: ~52000 Curles Noble Gas (Considered Xe-133) 1GW-TK-1B: ~52000 Curles Noble Gas (Considered Xe-133)
APPUCABILITY: At All 11mes ODCM SR DESCRIPTION PROCEDURE 4.11.2.5.1 Detennlne Tank Gas Contents when Fonn 1/2-HPP-3.06.003.F01: GW Tank Sampling Adding Rad Material & (RCS ActMty 1OM-19.4.G: GW Disposal System
>100uCl/mJ)
BV-2 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F: 12b 1/2-QDC-3,03, Attachment O Control 3.11.2.5: Maintain Gas storage Tank ActMty with the following llmlt:
2GWS-TK25A thru 25G: ~19000 Curies Noble Gas (Considered Xe-133) In any connected group of Gas Storage Tanks APPLICABILIJY: At All 11mes ODCM SR DESCRIPTION 4.11.2.5.1 Detennlne Gaseous Waste Tank Rad Material When Adding Rad Material to the Tank.
PROCEDURE Form 1/2-HPP-3.06.003.F01: GW Tank Sampling 2OM-19.2: GW Precautions & Limitations 2OM-19.4G: GW transfer from Unit 2 20M-54.3 L5 Loa Item 133
Beaver Valley Power Station Procedmc Number:
l/2-0DC-1.01
Title:
ODCM: Index, Matrix and History of ODCM Changes A TT ACH1\\1ENT C Page 16 of 19 Unit 1/2 Revision:
29 ODCM CONTROLS PROCEDURE MA1RIX BV-1 AND 2 GASEOUS EFFLUENT TREATMENT SURVEILLANCES TABLE F: 11 1/2-00C--3.03, Attachment N Control 3.11,2.4: Gaseous Effluent Treatment System APPLICABILITY: At All Times ODCM SR 4.112.
4.1 DESCRIPTION
PROCEDURE Fonn 1/2-ENV--05.05.F01: RWDA-G Level Of Use:
General Skill Reference Page Number:
111 of 114 Using the ODCM - Project the Gas Release Dose from the Site Every 31 Days Fonn 1/2-ENV--01.03.F01: Continuous Release Permit Fann 1/2--HPP-3.06.012.F01: Abnormal Gaseous Releases SAP Order (Issue NPD3NRE Letter. Monthly Dose Prolectlon)
Beaver Valley Power Station
Title:
Procedure Number:
l/2-0DC-1.01 Unit 1/2 Level OfUso:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
?.Q Page Number:
110 nf 114 ATTACHMENT C Page 15 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SURVEILLANCES TABLE F: 10 1/2-0DC-3.03, Attachment M Control 3.11.2,3: Gaseous Effluent Particulate And Iodine Doses APPUCABlLITY: At All Times ODCM SR 4.112.
3.1 DESCRIPTION
Using the ODCM - Determine the Particulate & Radlolodlne Cumulative Dose Contributions Every 31 Days PROCEDURE Fonn 1/2-ENV-05.05.F01: RWDA-G Fonn 1/2-ENV-01.03.F01: Continuous Release Pennlt Fonn 1/2-HPP-3.06.012.F01: Abnormal Gaseous Releases Fonn 1/2-HPP-4.02.002.F02: Rad Monitor Sampling SAP Order (Issue NPD3NRE Letter: Monthly Dose Projection)
Beaver Valley Power Station
Title:
Procedure Number:
1/2-0DC-l.0l Unit 1/2 Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
29 Page Number:
109 nf 114 ATTACHMENT C Page 14 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFWENT AIR DOSE SURVEJUANCES TABLE F: 9 1'2-0DC-3,03, Attachment L Control 3,112.2: Gaseous Effklent Air Doses APPUCABILllY: At All Times OOCM SR 4.11.2.
2.1 DESCRIPTION
Using the ODCM - Detennlne the Noble Gas Cumulative Dose Contributions Every 31 Days PROCEDURE Fann 1/2-ENV-05.05.F01: RWDA-G Fann 1/2-ENV-01.03.F01: Continuous Release Pennlt Fonn 1/2-HPP-3.06.012.F01: Abnormal Gaseous Releases Fann 1/2-HPP-4.02.002.F02: Rad Monitor Sampllng SAP Order {Issue NPD3NRE Letter: Monthly Dose p,rnv,.;,,,,J<>t-t....,..,..* n,'J
Beaver Valley Power Station Procedure Number:
l/2-0DC-1.01 Trtle:
Unit Level Of Use:
1 /?.
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number.
?Q Hl~ of 114 AITACIIMENT C Page 13 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT DOSE SURVEILLANCES TABLE F: 8 1~-0QC-3,Q~, Attach,:oo!Jl IS Cootl:QI ~.11,2,1: Gaseous Effklent Dose Rates APELICABll,,ITY: At All nmes OOCMSR 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-01.03F01: Continuous Release Permit Form 1/2-HPP-3.06.012.F01: Abnormal Gaseous Releases 1OM-19.4E, H: RWDA-G for Unit 1 GWDT's 1/20M-19.4AB: RWDA-G for Unit2 GWSTs 4.11.2.1.2 Sample and Analyze per Table 4.11-2 to Determine Inhalation Pathway Dose 4.11.2.1.2A Waste Gas Storage Tank -
Fonn 1/2-ADM-1611.F03 & F04: GW Tank Samp>>ng Grab Sample Each Tank Form 1/2-HPP-3.06.003.F01: GW Tanlc Sampttng Form 1/2-ENV-06.05.F01: RWDA-G fiorm 1/2-HPP-4.02.002.F02: Rad Monitor -
4.11.2.1.2.B Containment Purge -
Form 1/2-ADM-1611.F03 & F04: GW Tank Sampfing Grab Sample Each Purge Form 1/2-ENV-05.05.F01: RWDA-G Airborne Radioactivity Calculation Worksheet Form 1/2-HPP-4.02.002.F02: Rad Monitor Samottna 4.11.2. 1.2.C Ventilation Svstems 4.11.2.1.2.C.1 BV-1 Grab and Continuous Form 1/2-ADM-1611.F03 & F04: GW Tank SampMng thru Samples Form 1/2-ENV-01.03F01: Continuous Release Pennlt 4.11.2.1.C.3 Form 1 /2-HPP-4.02.002.F02: Rad Monitor Sampling and Form 1/2-HPP-4.02.017.F01-90: RMS & DRMS Valve Vertflcatlon 4.11.2.1.2.D.1 1-HPP-5.01.002: PING-4 Emergency Operation thru 4.11.2.1.2.D.3 4.11.2.1.2.C.4 BV-2 Grab and Continuous Form 1/2-ADM-1611.F03 & F04: GW Tank Sampffng thru Samples Form 1/2-ENV-01.03F01: Contlnll0ll8 Release Permit 4.11.2. 1.2.C.8 Form 1/2-HPP-4.02.002.F02: Rad Monitor SampRng and Form 1/2-HPP-4.02.017.F01-90: RMS & ORMS Valve Vertflcatlon 4.11.2.1.2.D.4 2-HPP-5.04.001: Emergency Operation of WRGM Assembly thru 4.11.2.1.2.D.8
(
J rl
(
('
ri -r
Beaver Valley Power Station Proccdarc Number:
1/2-0DC-l.0l Trtlo:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 12 of 19 Unit 1/2 Revision:
29 ODCM CONTROLS PROCEDURE MATRIX Level Of Use:
General Skill Reference Page Number.
107 nf 11A.
BV-1 AND 2 LIQUID STORAGE TANK ACTMTY LIMIT SURVEILLANCES TABLE F: 7 1/2-0DC-3.03. Attachment J Control 3.11.1.4: Maintain Liquid Tank Activity within the following Bmits:
~18 Curles In Unit 1 Primary Grade Water Storage Tank [1 BR-TK-6A]
~18 Curles In Unit 1 Primary Grade Water Storage Tank [1BR-TK-6B]
g Curies In Unit 1 steam Generator Drain Tank [1LW-TK-7A]
g Curies In Unit 1 Steam Generator Drain Tank [1LW-TK-7B]
§ Curies In Unit 1 RefueHng Water Storage Tank [1 QS-TK-1]
~62 Curles In Unit 2 Refueling Water Storage Tanlc [2QSS-TK21]
~10 Curies In Unit 1 and Unit 2 miscellaneous temporary outside radioactive Hquid storage tanks.
APPLICABILITY: At All nmes ODCM SR 4.11.1.
4.1 DESCRIPTION
Every 7 days Analyze a tank sample when radioactive material Is added to tanks except the RWSrs.
For RWSrs, analyze sample within 7 days of reactor cavity drain down back to the RWST.
PROCEDURE Form 1/2-HPP-3.06.001.F01: Activity Check Record Form 1/2-ENV-05.04.F01: RWDA-L 1 OM-8.4Z: Recirculate Test Tanks Thru Ion Exchanger 1OM-17.4.AJ: LW Transfer to 1LW-TK-7A&B 1 OM-54.3 LS Log Item 197:
1OM-54.3 L5 Log Item 132:
1 OM-54.3 L5 Log Item 134:
1 OM-54.3 L5 Log Item 200:
2OM-17.4B: LWto SG Slowdown Tank
Beaver Valley Power Station
Title:
Procedme Number:
1/2-0DC-l.0l Level Of Use:
j Unit 1n General Skill Reference ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 11 of 19 Revision:
?O ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT TREATMENT SURVEILLANCES TABLE F: 6 1/2-0DC-3.03, Attachment I Control 3.11.1,3: Liquid Effk.lent Treatment System APPLICABILITY: At All Times ODCM SR DESCRIPTION PROCEDURE Form 1/2-ENV-05.04.F01: RWDA-L PagcNumbcr.
]Oil nf 114 4.11.1.3.1 Using the ODCM - Project the Liquid Release Dose Every 31 Days SAP Order (Issue NPD3NRE Letter. Monthly Dose Projection) 1/2OM-17.4AD: RWDA-L
Beaver Valley Power Station Proccdurc Number:
l/2-0DC-1.01
Title:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 10 of 19 Unit 1/2 Rcvwon:
2Q ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFWENT DOSE SURVEILLANCES TABLE F: 5 1/2-0DC-3.03, Attachment H Control 3.11,1,2: Liquid Effluent Dose APPLICABILITY: At All Tones OOCM SR DESCRIPTION PROCEDURE Fonn 1/2-ENV-05.04.F01: RWDA-L Level Of Use:
General Skill Reference Pago Number:
104:i of 11A.
4.11.1.2.1 Using the ODCM - Detennlne Cumulative Dose From Liquid Effluents Everv 31 Davs SAP Order (Issue NPD3NRE Letter: Monthly Dose Projection) 1/20M-17.4A.D: RWDA-L
Beaver Valley Power Station Procedure Number:
1/2-0DC-l.0l
Title:
Unit Level OfUso:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Pago Numba:
?Q 104 nfl 14 ATTACHMENT C Page 9 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT CONCENTRATION SURVEILLANCES TABLE F:4 1/2-0DC--3.03. Attachment G Control 3.11,1,1: Maintain Effluent Concentratfon-wtthil 10 Times 10CFR20 EC's
~e PLICABl!:,ITY: At All Times ODCMSR DESCRIPTION PROCEDURE 4.11.1.1.1 A Batch Waste Release Tanks:
1/2-CHM-ANA-5.3: LW Compositing Sample and Analyze Radioactive Form 1/2-ADM-1611.F03 & F04: LW Tank Sampling, Liquid Wastes per Table 4.11-1 Form 1/2-HPP-3.06.001.F01: Activity Check Record Fonn 1/2-HPP-4.02.002.F02: Rad Monitor Sampling 4.11.1.1.1.B Continuous Releases:
Fonn 1/2-ADM-1611.F03 & F04: LW Tank Sampling, Sample and Analyze Radioactive Fonn 1/2-HPP-3.06.001.F01: Activity Check Record Llauld Wastes oer Table 4.11-1 Fonn 1/2-HPP-4.02.002.F02: Rad Monitor Samollna 4.11.1.1.2 Use ODCM Methodology to Assure Form 1/2-ENV-05.04.F01: RWDA-l Compfiance 1/2OM-17.4AD: RWDA-L 4.11.1.1.3 Take Turbine Bulldlng Grab Form 1/2-ADM-1611.F03 & F04: Sump Samplng, Sample When BV-1 Primary to Form 1/2-HPP-3.06.001.F01: Activity Check Record Secondary Leakage Exceeds 0.1 Fonn 1/2-ENV-05.04.F01: RWDA-L com (142 Qpd)
Fonn 1/2-HPP-4.02.002.F02: Rad Monitor SampllnQ 4.11.1.1.4 Obtain Turbine Building Grab Fonn 1/2-ADM-1611.F03 & F04: Sump SampRng, Sample When BV-2 Primary to Form 1/2-HPP-3.06.001.F01: Activity Check Record Secondary Leakage Exceeds 0.1 Form 1/2-ENV-05.04.F01: RWDA-l gpm (142 gpd)
Form 1/2-HPP-4.02.002.F02: Rad Monitor Sampling 4.11.1.1.5 Obtain Grab Samples Prior to BV-2 Fonn 1/2-ADM-1611.F03 & F04: Sump Samp~ng, Recirculation Drain Pump Form 1/2-HPP-3.06.001.F01: Activity Check Record Discharge to Catch Basin No. 16 2OM-9.2: Rx Plant Vents and Drains (CB-16) 2OM-9.4F: Drain RSS Pump Casing / Pit 2OM 51: OM Clearance 51-86 (2DAS-P215A/B)
Beaver Valley Power Station Procedure Number:
l/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:
?Q 1m ofl ]4 ATTACHMENT C Page 8 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3b 1/2-0DC-3.03, Attachment F Control 3,3.3,10: Maintain Gaseous Effluent Monitors In Table 3.3-13 OPERABLE APeLIQABll,,ITY: During Releases Through The Flow Paths ODCMSR DESCRIPTION PROCEDURE 4.3.3.10.3 Decontamination Building Vent NOTE: Actions for INOPERABLE monitors are documented In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.3.a Noble Gas Activity Monitor 2MSP-43.35-I: Channel Callbratlon Pri: (2RMQ-RQ3018) 2OST-43.9B: Channel Functional Test 2-HPP-4.02.018 Source Check (ORMS Auto Function)
Fonn 1/2-ADM-1611.F04: Channel Check 4.3.3.10.3.b Particulate & Iodine Sampler Form 1/2-ADM-1611.F04: Channel Check Pri: FIiter Paper and Charcoal Cartrldoe for (2RMQ-RQ301A) 4.3.3.10.3.d Sampler Flow Rate Monitor 2MSP-43.35-I: Channel Callbratlon Pri: (2RMQ-FIT301-1) 2MSP-43.35A-I: Chamel Operatlonal Test Form 1/2-ADM-1611.F04: Channel Check 4.3.3.10A DELETED 4.3.3.10.5 Waste Gu Storage Vault Vent NOTE: Actions for INOPERABLE monitors are documented In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.5.a Noble Gas Activity Monitor 2MSP-43.37-I: Channel Calibration P~: (2RMQ-RQ303B) 2OST-43.9D: Channel Functional Test Form 1/2-ADM-1611.F04: Channel Check 2-HPP-4.02.018 Source Check (ORMS Auto Function) 4.3.3.10.5.b Particulate & Iodine Sampler Fonn 1/2-ADM-1611.F04: Channel Check Pri: FIiter Paper and Charcoal Cartrkloe for (2RMQ-RQ303A) 4.3.3.10.5.d Sampler Flow Rate Monitor 2MSP-43.37-I: ChaMel Calibration Pri: (2RMQ-FIT303-1) 2MSP-43.37A-I Channel Operational Test Form 1/2-ADM-1611.F04: Channel Check C r -r -I'
Beaver Valley Power Station Procedure Number.
1/2-0DC-l.01
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number:
?Q 10? nf 114 ATTACHMENT C Page 7 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3b 1/2-0DC--3.03, Attachment F Control 3,3.3,10: Maintain Gaseous Effluent Monitors In Table 3.3-13 OPERABLE APELICABlblTY: During Releases Through The Flow Paths ODCMSR DESCRIPTION PROCEDURE 4.3.3.10 Test Monitors at Table 4.3-13 FreQuencv 4.3.3.10.1 SLCRS Unfiltered Pathway NOTE: Actions for INOPERABLE monHors are documented (Ventllatlon Vent)
In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.1.a Noble Gas Activity Monitor 2MSP-43.~: Channel Calibration Prl: (2HVS-RQ101B) 20ST-43.9A: Channel Functional Test Fonn 1/2-ADM-1611.F04: Channel Check 2-HPP-4.02.018 Source Check (DRMS Auto Function) 4.3.3.10.1.b Particulate & Iodine Sampler Form 1/2-ADM-1611.F04: Channel Check Prl: FIiter Paper and Charcoal Cartrldoe for (2HVS-RQ101A) 4.3.3.10.1.c Process Flow Rate Monitor 2MSP-43.~: Channel Calibration Prl: (Monitor Item 29 for 2HVS-2MSP-43.36A-I: Channel Operational Test VP101)
Work Request: Channel Calibration (Velocity Probe)
Form 1/2-ADM-1611.F04: Channel Check 4.3.3.10.1.d Sampler Flow Rate Monitor 2MSP-43.36-I: Channel Calibration Prl: (2HVS-FIT101-1) 2MSP-43.36A-I: Channel Operational Test Form 1/2-ADM-1611.F04: Channel Check 4.3.3.10.2 SLCRS Filtered Pathway NOTE: Actions for INOPERABLE monHors are documented (Elevated Release)
In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.2.a Noble Gas Activity Monitor 2MSP-43.32-I: 2HVS-RQ109A Channel Caftbratlon Prl: (2HVS-RQ109B) 2MSP-43.33-I: 2HVS-RQ109B,C,D Channel CaDbration 2OST-43.8: Channel Functional Test Form 1/2-ADM-1611.F04: Channel Check 2-HPP-4.02.018 Source Check (DRMS Auto Function) 4.3.3.10.2.b Particulate & Iodine Sampler Form 1/2-ADM-1611.F04: Channel Check Prl: Filter Paper and Charcoal Cartrldoe for (2HVS-RQ109A) 4.3.3.102.c Process Flow Rate Monitor 2MSP-43.32A-I: Channel Operational Test Prl: (Monitor Item 29 for 2HVS-2MSP-43.33-I: 2HVS-RQ109B,C,D, Channel Calibration FR22)
Form 1/2-ADM-1611.F04: Channel Check 1111Alt (2HVS-Fl22A and Fl22C) 2;"d Alt (2HVS-Fl22B and Fl22D) 4.3.3.10.2.d Sampler Flow Rate Monitor 2MSP-43.32-I: 2HVS-RQ109A Channel Caffbratlon Prl: (Monitor Items 28 & 72 for 2MSP-43.32A-I: Channel Operational Test 2HVS-DAU109A) 2MSP-43.33-I: 2HVS-RQ109B,C,D, Channel Calibration Form 1/2-ADM-1611.F04: Channel Check
Beaver Valley Power Station Proccdme Number:
l/2-0DC-1.01 Unit 1/2 Level OfUso:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
?.9 Page Number:
101 of 114 ATTACIIl\\.1ENT C Page 6 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F: 3a 1/2-0DC-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 4.3.3.10.3 Rx Containment/ SLCRS
{Elevated Release) 4.3.3.10.3.a Noble Gas Activity Monitor Prl: (RM-1VS-110 LRNG Rel)
Alt (RM-1VS-107B) 4.3.3.10.3.b Particulate & Iodine Sampler Pri: Riter Paper and Charcoal Cartridge for (RM-1VS-110)
A~ Filter Paper and Charcoal Cartridge for (RM-1VS-107) 4.3.3.10.3.c System Effluent Flow Rate Measuring Device Prl: (FR-1VS-112)
Aft (RM-1VS-110 LR STK FL) 4.3.3.10.3.d Sampler Flow Rate Measuring Device Prl: (ABPM-1VS-110-PISFlow)
Aft (Rotameter for RM-1VS-107)
PROCEDURE NOTE: Actions for INOPERABLE monitors are documented In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 1 MSP-43.20-I: Channel Calibration 1OM-54.3 L5 Log: RM-1VS-107B Channel Check 1OST-43.7A: RM-1VS-110 Channel Functional Test 1 OST-43.9L: Channel Functional Test 10ST-43.9A: Source Check Fonn 1/2-ADM-1611.F03: Channel Check Fonn 1 /2-ADM-1611.F03: Channel Check 1 MSP-44.09-I: Channel Calibration 1MSP-44.10-I: Channel Operational Test Fonn 1/2-ADM-1611.F03: Channel Check 1 MSP-43.19-I: ChSMel Calibration Fonn 1/2-ENV-01.04.F01: Channel Operational Test Fonn 1/2-ADM-1611.F03: Channel Check
Beaver Valley Power Station
~
Number:
l/2-ODC-1.01
Title:
Unit Level OfU,e:
1/2 General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Rcvis:lon:
Page Number:
?.Q 100 of 114 ATTACHMENT C Page 5 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS EFFLUENT MONITOR SURVEILLANCES TABLE F: 3a 1/2-0DC-3.03. Attachment F Control 3,3.3.10: Malntaln Gaseous Effluent Monitors In Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths OOCMSR DESCRIPTION PROCEDURE 4.3.3.10 Test Monitors at Table 4.3-13 FreQuencv 4.3.3.10.1 Gaseous Waste / Process Vent NOTE: Actions for INOPERABLE monitors are documented System In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.1.a Noble Gas Activity Monitor 1 MSP-43.22-I: Channel Calibration Pri: (RM-1GW-1088) 1OM-19.4.E, H: Channel Check {Batch Release)
Alt: {RM-1GW-109 LRNG Rel): for 10M-19.4.E, H: Source Check continuous releases only, not an 1/2-0M-19.4A.D: Source Check alternate for batch releases 1/2-0M-19.4A.D: Channel Check {Batch Release) 10ST-43.9D: Channel Functional Test 10ST-43.7A: RM-1GW-109 Channel Functional Test Form 1/2-ADM-1611.F03: Channel Check 4.3.3.10.1.b Particulate & Iodine Sampler Fonn 1/2-ADM-1611.F03: Channel Check Pri: FIiter Paper and Charcoal Cartridge for (RM-1GW-109)
Alt: Filter Paper and Charcoal Cartrldae for (RM-1 GW-108) 4.3.3.10.1.c System Effluent Flow Rate 1MSP-19.05-I: Channel Operational Test Measuring Device 1 MSP-19.06-I: Channel Calibration Pri: (FR-1GW-108)
Form 1/2-ADM-1611.F03: Channel Check Alt (RM-1GW-109 LR STK FL) 4.3.3.10.1.d Sampler Flow Rate Measuring 1 MSP-43.21-I: Channel Calibration Device Form 1/2-ENV-01.04.F01: Channel Operational Test Pri: (ABPM-1GW-109-PISF!ow)
Form 1/2-ADM-1611.F03: Channel Check Alt: (RotameterforRM-1GW-108) 4.3.3.10.2 Auxlllary Building VentllaUon NOTE: Actions for INOPERABLE monitors are documented System (Ventllatlon Vent)
In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.05 4.3.3.10.2.a Noble Gas Activity Monitor 1 MSP-43.13-I: Channel Calibration Pri: (RM-1VS-109 LRNG Rel) 1OST-43.7A: RM-1VS-109 Channel Functional Test Alt: (RM-1VS-101B) 1 OST-43.9J: Channel Functional Test 1 OST -43.9A: Source Check Form 1/2-ADM-1611.F03: Channel Check 4.3.3.10.2.b Particulate & Iodine Sampler Form 1/2-ADM-1611.F03: Channel Check Pri: FIiter Paper and Charcoal Cartridge for (RM-1VS-109)
Alt: FIiter Paper end Charcoal Cartridae for (RM-1VS-101) 4.3.3.10.2.c System Effluent Flow Rate 1MSP-44.07-I: Channel Operational Test Measuring Device 1MSP-44.08-I: Channel Calibration Pri: (FR-1VS-101)
Form 1/2-ADM-1611.F03: Channel Check Alt: (RM-1VS-109 LR STK FL) 4.3.3.10.2.d Sampler Flow Rate Measuring 1MSP-44.07-I: Channel Functlonal Test Device 1 MSP-44.08-I: Channel Callbratlon Pri: (ABPM-1VS-109-PISFlow)
Form 1/2-ENV-01.04.F01 Channel Operational Test Alt: <FT-1RM-101 & Fl-1RM-101)
Form 1/2-ADM-1611.F03: Channel Check
Beaver Valley Power Station Proccdare Nwnber:
l/2-0DC-1.01
Title:
Unit Lovcl.OfUsc:
1 /?.
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Revision:
Page Number.
?Q 99 nfl 1.1 ATTACHMENT C Page 4 of 19 ODCM CONTROLS PROCEDURE MATRIX I
BV-2 LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F: 2b 1/2-0DC-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 ODCMSR DESCRIPTION PROCEDURE 4.3.3.9 Test Monitors at Table 4.3-12 Freauencv 4.3.3.9.1 Monitors Providing Alann and NOTE: Actions for INOPERABLE monitors are documented Automatic Tennlnatlon In the Oneratlons & Rad Effluent Shift l..nn.K.
4.3.3.9.1.a Liquid Waste Process Effluent Form 1/2-ADM-1611.F04: Channel Check Monitor Form 1/2-ENV-05.04.F01: Source Check (2SGC-RQ100) 2MSP-43.39-I: Channel Calibration 1/2OM-17.4A.C: Source Check 2OM-25.4.L: Source Check 20M-25.4.N: Source Check 2OST-43.3: Channel Functional Test 4.3.3.9.2 Flow Rate Measurement Devices NOTE: Actions for INOPERABLE monitors are documented In the Operations & Rad Effluent Shift Logs and 1/2-ENV-05.04 4.3.3.92.a Liquid Radwaste Effluent 2MSP-25.01-I: 2SGC-P26A,B Channel Calbration (2SGC-FIS100) 2MSP-25.01-l: 2SGC-P26A,B Channel Operational Test 2MSP-43.39-I: Channel Callbratlon Form 1/2-ADM-1611.F04: Channel Check 2OM-54.3 L5 Loa: Channel Check 4.3.3.9.2.b Cooling Tower Slowdown Line 1MSP-31.04-I: FT-CW-101 Channel Callbratlon Pri: [FT-1CW-101-1]
1MSP-31.~: FT-CW-101 Channel Operational Test Alt [FT-1CW-101] and [2CWS-FT101]
1MSP-31.06-I: FT-CW-101-1 Chamel Csllbratlon 1MSP-31.07-I: FT-CW-101-1 Chamel OperaUonaJ Test 2MSP-31.04-I: 2CWS-FT101 Channel Cslbratlon 2MSP-31.05-I: 2CWS-FT101 Chemel Operational Test 1OM-54.3 L5 Log: FT-CW-101-1 & FT-CW-101 Channel Checks 20M-54.3 L5 Lnn: 2CWS-FT101 Channel Check
Beaver Valley Power Station Trtlo:
Procedure Number:
l/2-ODC-1.01 Unit Level Of Use:
General Skill Reference ODCM: Index, Matrix and History of ODCM Changes Rovwon:
Pago Number.
ATTACHMENT C Page 3 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F: 2a 1/2-0DC-3.03. Attachment E Control 3.3.3.9: Maintain Liquid Effluent Monitors In Table 3.3-12 OPERABLE APPUCABlUTY: During Releases Through The Flow Path OOCMSR DESCRIPTION PROCEDURE 4.3.3.9 Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1 Monltona Provkllng Alarm and NOTE: Actions for INOPERABLE monitors are documented In the Automatic TermJnatlon
. * -- & Rad Effluent Shift l.oas.
4.3.3.9.1.a Liquid Radwaste Effluent Line 1MSP-43.18-I: ChaMel Calibration (RM-1LW-104)
Form 1/2-ENV-05.04.F01: Source Check 1/20M-17.4AD: Source Check 10M-17.4.AK Source Check 1 OST-43.9F: Channel Functional Test Form 1/2-ADM-1611.F03: Channel Check 4.3.3.9.1.b Liquid Waste Contaminated Drain Line 1MSP-43.23-l: Chaooel Callbratlon (RM-1LW-116)
Fann 1/2-ENV--05.04.F01: Source Chec:k 1/20M-17.4AD: Source Check 10ST-43.9G: Channel Functlonel Test Fonn 1/2-ADM-1611.F03: Channel Check 4.3.3.9.2 Monitors Providing Alarm, but Not NOTE: ActloM for INOPERABLE monitors are documented In the Provkllno Auto Termination OnArations & Rad Effluent Shift Loas.
4.3.3.9.2.a Component Coollng - Rec/rcu/atlon 1MSP-43.10-1: Channel Calibration Spray Hx River WatN Monitor 1OST-43.9H: Channel Functional Test (RM-1RW-100) 10ST-43.9A: Source Check Form 1/2-ADM-1611.F03: Channel Check 4.3.3.9.3 Row Rate Measurement Devices NOTE: Actions for INOPERABLE monitors 81'9 documented In the ODemlons & Rad Effluent Shift Loos and 1/2-ENV-05.04 4.3.3.9.38,b Liquid Radwaste Effluent Lines 1MSP-17.05-I: Channel Calibration (3b) 3a: (FR-1LW-104 for RM-1LW-104) 1MSP-17.08-I: F-LW-104-1 Channel Callbratlon (3e) 3b: (FR-1LW-103 for RM-1LW-116) 1MSP-17.07-I: F-LW-104-2 Channel Calibration (3a) 1MSP-17.08-I: F-LW-104-1 Channel Operational Test (3a) 1MSP-17.09-I: F-LW-104-2 Channel Operational Test (3a) 1MSP-17.10-I: F-LW-103 Channel Operational Test (3b)
Form 1/2-ADM-1611.F03: Channel Check 10M-54.3 L5 Loa: FR-1LW-104 & FR-1LW-103 Channel Checks 4.3.3.9.3.c CooUng Tower Blowdown Line 1MSP-31.04-I: FT-CW-101 Channel Calibration Prl: [FT-1CW-101-1]
1 MSP-31.05-I: FT-CW~101 Channel Operational Test Alt [FT-1CW-101] end [2CWS-FT101]
1MSP-31.06-I: FT-CW-101-1 Channel Caibratfon 1MSP-31.07-I: FT-CW-101-1 Channel Operatlonel Test 2MSP-31.04-I: 2CWS-FT101 Channel Calibration 2MSP-31.05-I: 2CWS-FT101 Channel Operational Test 1OM-54.3 L5 Log: FT-CW-101-1 & FT-CW-101 Channel Checks 20M-54.3 L5 Loa: 2CWS-FT101 Channel Check 4.3.3.9.4 Tank Levef Indicating Devices NOTE: Actions for INOPERABLE monitors are documented In the
,,. Shift Loaa 4.3.3.9.4.e Primary Water Storage Tank 1 MSP-8.01-1: L-PG115A Channel Operational Test (Ll-1PG-115A for 1BR-TK-6A) 1MSP-8.03-I: L-PG115A Channel Cellbratlon 1OM-54.3 L5 Lna: Chamel Check (When Adding to Tank) 4.3.3.9.4.b Primary Water Storage Tank 1MSP-8.02-I: L-PG-1158 Channel Operational Test (U-1 PG-1158 for 1 BR-TK-68) 1 MSP-8.04-I: L-PG-1158 Channel Calibration 1 OM-54.3 L5 Loa: Channel Check (Vi/hen Addlna to Tank) 4.3.3.9.4.c Steam Generator Drain Tank 1MSP-17.01-I: L-LW110 Channel OperetioneJ Test (Ll-1LW-110 for 1LW-TK-7A) 1MSP-17.03-I: L-LW110 Channel Callbratlon 1OM-54.3 L5 Loa: Channel Check /When Addlno to Tank) 4.3.3.9.4.d Steam Generator Drain Tank 1MSP-17.02-I: L-LW111 Channel Operational Test (Ll-1LW-111 for 1LW-TK-7B) 1MSP-17.04-I: L-LW111 Channel CaDbratlon 1OM-54.3 LS Loa: ChaMel Check (When Addlna to Tank)
C
lu Beaver Valley Power Station Procedure Number:
l/2-0DC-1.01
Title:
ODCM: Index, Matrix and History of ODCM Changes ATTACHMENT C Page 2 of 19 Unit 1/2 Revision:
?Q ODCM CONTROLS PROCEDURE MATRIX BV-2 RADIATION MONITORING INSTRUMENTION SURVEILLANCES TABLE F: 1b LcvclOfUsc:
General Skill Reference Page Number.
97 of 114 1/2-0DC--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 4.3.3.1 Test Monitors at Table 4.3-3 Frequency 4.3.3.1.1 Noble Gas Effluent Monitors 4.3.3.1.2.c.i.1.1.a Supplementary Leak Collectlon and Release System (2HVS-RQ109C & D)
PROCEDURE NOTE: Actions for INOPERABLE Monitors are documented In the Ooeratlons & Rad Effluent Shift Logs.
2MSP--43.33-I: Channel Calibration Fonn 1/2-ADM-1611.F04: Channel Check 20ST-43.8: Channel Ooeratlonal Test