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Category:Report
MONTHYEARML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 2024-01-08
[Table view] Category:Miscellaneous
MONTHYEARNL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) ND-18-1500, CFR 50.46 Thirty Day Report2018-12-18018 December 2018 CFR 50.46 Thirty Day Report ML18152B7852018-10-12012 October 2018 Summary of Nuclear Regulatory Commission Vendor Inspections Affecting Inspections, Tests, Analyses, and Acceptance Criteria ND-18-1047, Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule2018-08-0808 August 2018 Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule NL-18-0670, Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements2018-05-24024 May 2018 Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements NL-17-1889, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information2017-12-0505 December 2017 NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information NL-17-0777, Flooding Focused Evaluation Summary Report2017-06-30030 June 2017 Flooding Focused Evaluation Summary Report NL-17-0218, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment2017-03-27027 March 2017 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment NL-15-2276, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20142015-12-23023 December 2015 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ND-14-2009, 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-12-17017 December 2014 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20132014-12-0808 December 2014 Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 ML14279A3522014-11-0606 November 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14169A5992014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14049A3542014-02-24024 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML13162A5342013-06-10010 June 2013 Initial Exam 2013-301 Final SRO Written Exam NL-13-0173, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-12-0324, Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-00062012-02-16016 February 2012 Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-0006 NL-11-0626, Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-0062011-03-29029 March 2011 Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-006 NL-10-1536, Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-0062010-08-18018 August 2010 Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-006 ML1015903342010-06-0808 June 2010 Audit of Steam Generator H Amendment Reference Documents ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants NL-09-1449, Submittal of Emergency Response Data System (Eros) Data Point Library Modification2009-09-24024 September 2009 Submittal of Emergency Response Data System (Eros) Data Point Library Modification NL-09-1375, Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.102009-08-25025 August 2009 Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.10 NL-08-1405, Report of Unsatisfactory Performance Testing2008-09-12012 September 2008 Report of Unsatisfactory Performance Testing NL-08-0343, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment2008-03-18018 March 2008 Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment NL-07-1777, Supplemental Response to NRC Generic Letter 2004-022008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02 NL-08-0275, Response to 01/28/2008 Request for Additional Information2008-02-27027 February 2008 Response to 01/28/2008 Request for Additional Information ML0732405912007-11-0505 November 2007 Land Management Plan ML0732407392007-11-0505 November 2007 Stratigraphy and Depositional Environments of Sediments from Five Cores from Screven and Burke Counties, Georgia ML0732403812007-11-0505 November 2007 10 CFR 50.75(g) Leak/Spill Decommissioning Record, Figure 1, for 1980s and 1990s, NMP-EN-002, Version 1.0 2024-01-12
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Text
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 1 of 9 Printed November 1, 2007 at 8:40 PRB REVIEW REQUIRED
RADIOACTIVE WASTE MINIMIZATION PROGRAM
PROCEDURE USAGE REQUIREMENTS- SECTIONS Continuous Use: Procedure must be open and readily available at the work location. Follow procedure step by step
unless otherwise directed.
Reference Use:
Procedure or applicable sect ion(s) available at the work location for ready reference by person
performing steps.
Information Use:
Available on plant site for reference as needed.
ALL Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 2 of 9 Printed November 1, 2007 at 8:40
1.0 PURPOSE
This procedure establishes the responsibilities, methods, and work practices for the radioactive waste volume minimization program at VEGP. The objectives of the program are to minimize: (1986307614, 1986207614)
- a. The volume of solid and liquid radioactive waste generated.
- b. The number of contaminated areas.
- c. The amount of contam inated tools and equipment.
2.0 DEFINITIONS
RADIATION CONTROLLED AREA (RCA)
Any area which contains or potentially contains radiation, contamination, or radioactive materials in quantities or levels sufficient to require posting of protective measures.
3.0 RESPONSIBILITIES
3.1 PLANT
OPERATIONS ASSISTANT GENERAL MANAGER
3.1.1 Establishes
and maintains the radioac tive waste volume minimization program.
3.1.2 Establishes
goals for solid and liquid radioactive waste reduction.
3.1.3 Assigns
specific responsibilities for the implementation of the program.
3.1.4 Dedicates
personnel to ensure proper attention and review of the program.
3.2 DEPARTMENT
MANAGERS
3.2.1 Consider
and include radioactive waste volume reduction methods in work planning and coordination activities.
3.2.2 Review, as appropriate, plant instructions or procedures associated with the implementation of the radioactive waste volume reduction program.
3.2.3 Ensure
departmental personnel receive training in radioactive waste reduction, decontamination methods and work practices prior to working in Radiation Controlled Areas.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 3 of 9 Printed November 1, 2007 at 8:40
3.2.4 Periodically
check materials entering the RCA to prevent the entry of unnecessary disposable materials.
3.2.5 Conduct
plant tours, adhering to the frequency and requirements of Procedure 00254-C, "Foreign Material Exclusion And Plant Housekeeping Programs," to ensure compliance with the program. Ensure that all leaks in area of responsibility are properly contained and that a Work Order has been written and/or the leak has been report ed to the Shift Supervisor.
3.2.6 Facilities
Group 3.2.6.1 Collects and transfers trash and laundry from collection locations to the interim storage area as needed.
3.2.6.2 Ensures trash, laundry and reusable item receptacles are properly identified (by signs and/or color coding) and pl aced throughout the plant as needed.
3.2.6.3 Ensures that only approved decontamination methods and permissible chemicals are used.
3.2.6.4 Evaluate the generation of additional radwaste and additional exposure to personnel against the limits of reduced personnel exposure and contamination levels when prescribing methods and ex tent of decontamination efforts.
3.3 HEALTH
PHYSICS MANAGER The Health Physics Manager is responsible for ensuring the following groups perform the indicated functions.
3.3.1 Health
Physics Section 3.3.1.1 Surveys all materials prior to removal from the RCA.
3.3.1.2 Ensures that radioactive materials are packaged in a manner which precludes the spread of contamination.
3.3.1.3 Labels containers of radioactive ma terials with the contents, radiation and contamination levels and the initials of the surveyor.
3.3.1.4 Routinely performs and reviews contamination surveys to determine area contamination levels and to monitor the radiological conditions of contaminated areas.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 4 of 9 Printed November 1, 2007 at 8:40 3.3.1.5 Assigns priorities for decontamination based upon area entry frequency, equipment usage, contamination levels, and planned work activities in the area.
3.3.1.6 Identifies tools and equipment with fixed contamination by spraying them with hot magenta paint.
3.3.1.7 Requires the use of containment devices where practical to prevent the spread of contamination.
3.3.1.8 Designates criteria for color-c oding and labeling receptacles for clean and contaminated trash, laundr y, and reusable items.
3.3.1.9 Designates and establishes laydown and/or storage areas for liquid (wet) and/or bulky contaminated items.
3.3.1.10 Implements a sorting and monitoring program to separate contaminated from non-contaminated material and recover reusable items.
3.3.1.11 Establishes a program to moni tor and trend solid radioactive waste.
3.3.1.12 Maintains an on-going program to investigate processing methods and techniques that will result in the improved processing and volume reduction of radioactive waste.
3.3.1.13 Establishes stringent demineralizer and filter change-out criteria for low flow, high radiation level, and high differential pressure.
3.3.1.14 Establishes program to track Work Orders for leaking components to ensure timely corrective action is taken.
3.3.1.15 Provides guidance to plant personnel regarding appropriate waste-minimizing work practices.
3.4 TEAM LEADER/ASSISTANT TEAM LEADER The Team Leader/Assistant Team Leader ensures the Performance Team work planner reviews WOs before starting work; establishes a list of tasks to be performed (valve packing, pump repair, etc.) and a list of minimum equipment/parts required to perform the tasks to prevent carrying unnecessary equipment into the RCA.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 5 of 9 Printed November 1, 2007 at 8:40
3.5 PLANT
TRAINING AND EM ERGENCY PREPAREDNESS MANAGER The Plant Training and Emergency Preparedness Manager ensures the following:
3.5.1 Personnel
are instructed in radioactive waste minimization methods and good radiological work practices in General Employee Training and Radiation Worker Training classes.
3.5.2 Personnel
awareness of the VEGP radioactive waste minimization program and emphasizes each individual's responsibilities for making the program effective.
3.6 OPERATIONS
MANAGER The Operations Manager ensures the following:
3.6.1 Radioactive
waste processing equipment is operated in a safe and efficient manner.
3.6.2 An on-going program is maintained to investigate processing methods and techniques that will result in the improved processing and volume reduction of radioactive waste.
3.6.3 Stringent
demineralizer and filter change-out criteria are established for low flow, high radiation level, and high differential pressure.
3.6.4 Where
possible, leaking components ar e isolated until proper corrective action can be taken.
3.6.5 Guidance
is provided to plant personnel regarding appropriate waste-minimizing work practices.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 6 of 9 Printed November 1, 2007 at 8:40
3.7 PLANT
PERSONNEL Radioactive waste volume minimization is the responsibility of all personnel.
3.7.1 Observe
all instructions and procedures pertaining to radioactive waste minimization methods and work practices.
3.7.2 Report
leaking components to personnel in the Control Room or Health Physics and, where practical take steps to contain the leak.
3.7.3 No one should bring unnecessary disposable material into the RCA.
3.7.4 Each individual is responsible for removal of all tools, equipment and trash brought into the work area by them or their work group per Procedure 00254-C.
3.7.5 Personnel
contaminating an area, due to negligence on the workers' part, shall be held responsible for the dec ontamination of the area.
4.0 PROCEDURE
4.1 MATERIAL
CONTROL METHODS The following practices should be implemented to control the volume of radioactive waste generated in the RCA.
4.1.1 Unpack
material to the extent practicable prior to transport into the RCA. Only the packaging required for protection or cleanliness concerns should be left on the materials.
4.1.2 Take into the RCA only those tools and supplies necessary to perform a specific task.
4.1.3 Retain
tools and equipment previously used in contaminated areas in the Hot Tool Room for use in other contaminated areas to prevent the need for contaminating clean tools and equipment.
4.1.4 Restrict
the use of disposable pr otective clothing in contaminated areas.
4.1.5 Perform
work in clean areas prior to entry into the RCA whenever practicable. Prefabrication should be maximized in order to decrease the volume of contaminated material produced.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 7 of 9 Printed November 1, 2007 at 8:40
4.1.6 Avoid
the use of porous materials which are difficult to decontaminate and/or release from the RCA.
4.1.7 Wrap tools and equipment, where practical, to preclude need for decontamination efforts.
4.1.8 Use only the quantity of material necessary for wrapping or bagging contaminated materials.
4.1.9 Verify
the radiological condition of ma terials being removed from the RCA prior to their disposal.
4.1.10 Limit the number of points of access of material into RCA.
4.2 WASTE
COLLECTION AND SEGREGATION METHODS The following methods should be implemented to facilitate the collection and subsequent segregation of radioacti ve wastes from clean wastes.
4.2.1 Provide
separate color-coded and label ed containers for the collection of contaminated material, clean material, and reusable items.
4.2.2 Have all waste material and laundry generated at control points monitored prior to removal from the area to separate highly contaminated material from material with little contamination.
4.2.3 Label
tools and equipment for decon or re-use in a manner by which they can be easily identified.
4.2.4 Make provisions for the proper handling and removal of contaminated or potentially contaminated equipm ent from the job site prior to commencing work.
4.2.5 Provide
"Clean Trash" receptacles at entrances to the RCA to help minimize the amount of clean materials entering the RCA.
4.2.6 Aerosol
cans, paint cans, wet mop heads and other wet trash generated in Radiation Controlled Areas are not to be disposed of in yellow drums. These items will be bagged separately and deposited in a storage area designated by HP Supervision for proper disposal.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 8 of 9 Printed November 1, 2007 at 8:40
4.3 CONTAMINATION
CONTROL METHODS
4.3.1 Determine
the source of contamination and take steps to correct the cause prior to performing extensive decontamination.
4.3.2 Where
necessary, implement a program of periodic decontamination of high use areas.
4.3.3 Use containment devices, where practicable, to prevent the spread of contamination.
4.3.4 Pre-plan work and practice good housekeeping when working in contaminated areas.
4.3.5 Report
potential or actual sources of contamination to Health Physics or to the control room.
4.4 LIQUID
RADWASTE MINIMIZATION METHODS
4.4.1 Isolate
and drain syst ems prior to breaching.
4.4.2 Use the smallest volume of liquid practical for flushing components or equipment.
4.4.3 Follow
posted instructions on drains, valves, and vents, etc.
4.4.4 Report
leaking components to personnel in Health Physics and the Control Room, and, where possible, take steps to contain the leak.
4.4.5 Do not use floor drains for discarding solvents and oils.
4.4.6 Report
any accumulation of water on the floor of the Auxiliary Fuel Handling, Radwaste or Containment buildings to Health Physics or Control Room personnel.
4.5 WASTE
SORTING AND MONITORING METHODS 4.5.1 Have all material monitored by Health Physics personnel prior to its removal from the RCA.
4.5.2 Sort waste into "contaminated" and "clean" containers to minimize the volume of radioactive waste which must be processed.
Approved By T. E. Tynan Vogtle Electric Generating Plant Procedure Number Rev 00256-C 7.1 Date Approved 06/28/2005 RADIOACTIVE WASTE MINIMIZATION PROGRAM Page Number 9 of 9 Printed November 1, 2007 at 8:40
5.0 REFERENCES
5.1 INPO Good Practice No. 82-001-OEN-09, Sept. 1982, "Low Level Radioactive Waste Management"
5.2 Procedure
00254-C, "Foreign Material Exclusion And Plant Housekeeping Programs" 5.3 COMMITMENTS, AND ACTION ITEMS
5.3.1 Commitments
1986307614
5.3.2 Action
Items 1986207614
END OF PROCEDURE TEXT