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Category:Graphics incl Charts and Tables
MONTHYEARL-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2018-067, Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table L-2016-109, Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information2016-05-11011 May 2016 Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15321A0632015-12-10010 December 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T NRC 2014-0029, CFR 50.46 Annual Report/30-Day Report2014-04-18018 April 2014 CFR 50.46 Annual Report/30-Day Report ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 NRC 2008-0078, Status of Action Plans Taken in Response to Confirmatory Order EA-06-1782008-11-11011 November 2008 Status of Action Plans Taken in Response to Confirmatory Order EA-06-178 L-2008-002, Corporate Merger of Decommissioning Trustee2008-01-0303 January 2008 Corporate Merger of Decommissioning Trustee ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0514002682004-10-0808 October 2004 Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material ML0421800522004-07-30030 July 2004 E-mail from: Allyn Pratt, to: Stacey Imboden, Manitowoc County ML0520301912004-06-0101 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520301982004-06-0101 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520301712004-05-31031 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520301812004-05-31031 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520302152004-05-30030 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520302092004-05-30030 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520301942004-05-29029 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520301992004-05-29029 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520302032004-05-28028 May 2004 U1R28 ML0520301742004-05-28028 May 2004 Plan-of-the-Day Meeting ML0508303902004-05-28028 May 2004 E-Mail K. Locke, NMC, to H. Chernoff, NRR, CE013955 & Pbnp Extent Cond. Eval. 2004 ML0519600552004-05-20020 May 2004 U1R28 OCC Interactive Turnover with Handwritten Notations ML0519600572004-05-20020 May 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0519600622004-05-20020 May 2004 Plan-of-the-day Meeting, with Handwritten Notations ML0519903882004-05-19019 May 2004 Plan-of-the-day Meeting, with Handwritten Notations ML0519903862004-05-19019 May 2004 U1R28 OCC Interactive Turnover ML0519903732004-05-18018 May 2004 Plan-of-the-Day Meeting ML0519505902004-05-17017 May 2004 Plan-of-the-day Meeting, with Handwritten Notations ML0508303252004-05-0505 May 2004 E-Mail A. Keim, NRR, to H. Chernoff, NRR, Point Beach Requested Order Relaxation ML0508401632004-04-30030 April 2004 Corrective Maintenance Backlog ML0519200422004-04-12012 April 2004 U1R28 OCC Interactive Turnover (with Handwritten Notes) ML0519200402004-04-12012 April 2004 U1R28 OCC Interactive Turnover with Handwritten Notations ML0519200432004-04-12012 April 2004 Plan-of-the-Day Meeting ML0519200382004-04-11011 April 2004 U1R28 OCC Interactive Turnover ML0519200372004-04-11011 April 2004 U1R28 OCC Interactive Turnover ML0519200362004-04-10010 April 2004 U1R28 OCC Interactive Turnover ML0508405102004-04-0909 April 2004 Attachment 1: Pbnp SG Nozzle Dam Installation & Vent Path Timeline ML0518904632004-04-0909 April 2004 Plan-of-the-Day Meeting ML0518904372004-04-0909 April 2004 U1R28 OCC Interactive Turnover ML0518904342004-04-0909 April 2004 U1R28 OCC Interactive Turnover Handwritten Notations ML0518904662004-04-0808 April 2004 U2R28 OCC Interactive Turnover ML0518904682004-04-0808 April 2004 Plan-of-the-Day Meeting ML0518904742004-04-0808 April 2004 U1R28 OCC Interactive Turnover ML0518904492004-04-0707 April 2004 U1R28 OCC Interactive Turnover ML0518904572004-04-0707 April 2004 Plan-of-the-Day Meeting with Handwritten Notations ML0508800932004-04-0303 April 2004 Licensee'S Radiological Survey ML0508401642004-04-0202 April 2004 U1R28 OCC Interactive Turnover Meeting Agenda 04/02/04 2024-03-13
[Table view] Category:Operating Procedures
MONTHYEARL-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2012-323, Strainer Fiber Bypass Test Protocol2012-08-10010 August 2012 Strainer Fiber Bypass Test Protocol ML0432803242004-11-22022 November 2004 ATC Operating Instruction Revision 1: Transmission Line Right-of-Way Forestry Specification ML0508800622004-05-0707 May 2004 Licensee Procedure, HPIP 4.58, Issuance of Respiratory Equipment Revision 14 ML0519202202004-04-21021 April 2004 Np 8.4.10 Exclusion of Foreign Material from Plant Components and Systems ML0508800702004-03-19019 March 2004 Licensee Procedure HPIP 4.58 Issuance of Respiratory Equipment, Revision 13 ML0306305382003-02-0606 February 2003 AFW Pump Normal Operation and Testing Pre-job Briefing Requirements ML0307900602002-10-30030 October 2002 Temporary Change Review and Approval, OI 62B, Turbine-Driven Auxiliary Feedwater System (P-29) ML0307900822002-10-30030 October 2002 Temporary Change Review and Approval, OI 62A, Rev 21, Motor-Driven Auxiliary Feedwater System (P-38A and P-38B ML0308708072002-10-29029 October 2002 Temporary Change Review and Approval, ECA-0.0, Rev 31, Loss of All AC Power ML0308708022002-10-24024 October 2002 Procedure Record and Field Copy Tracking, Procedure IT 10, Rev 45 ML0308707862002-10-23023 October 2002 Procedure Record and Field Copy Tracking, Procedure IT 10, Rev 45 ML0307707102002-10-0606 October 2002 Procedure IT 300B, Rev. 10, S/G B Mf Line Check Valves (Csd) Unit 1 ML0307706382002-09-25025 September 2002 Temporary Change Review & Approval, OM 4.3.2, Eop/Aop Verification/Validation Process ML0307706202002-09-25025 September 2002 Temporary Change Review & Approval OM 4.3.1, Rev. 5, AOP & EOP Writer'S Guide. ML0307703972002-09-16016 September 2002 OI 150, Rev. 1, Heating Condensate Storage Tanks. ML0308707002002-06-0303 June 2002 Page 14 of Abnormal Operating Procedure AOP-5B, Revision 21, Loss of Instrument Air ML0308706902002-05-16016 May 2002 Page 12 of Abnormal Operating Procedure AOP-10A, Revision 33, Safe Shutdown - Local Control ML0307307472002-03-0606 March 2002 Plant Procedure Np 7.2.3, Engineering Change Requests, Revision 6 ML0307307382002-02-18018 February 2002 Pages 6 & 8 of Abnormal Operating Procedure AOP-1 0, Control Room Inaccessibility ML0307307362002-02-18018 February 2002 Pages 1-18 of Abnormal Operating Procedure AOP-1 0, Control Room Inaccessibility ML0308705662002-02-0606 February 2002 Temporary Change Review and Approval, IT 10, Temp Change No. 2002-0048 ML0308705592002-02-0606 February 2002 Temporary Change Review and Approval, IT 10, Temp Change No. 2002-0047 ML0307307312002-02-0606 February 2002 Temporary Change Review and Approval, IT 10, Rev 43, Temp Change No. 2002-0048 ML0508800612002-02-0606 February 2002 Licensee Procedure HPIP 4.40 TEDE ALARA Evaluation, Revision 0 2023-06-09
[Table view] Category:Report
MONTHYEARL-2023-089, Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections L-2023-028, And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions ML21126A2392021-05-0606 May 2021 Subsequent License Renewal Application, Aging Management Supplement 2 ML21040A4842021-02-0909 February 2021 Fws to NRC, Point Beach Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location And/Or May Be Affected by Your Project ML21040A4852021-02-0909 February 2021 Fws to NRC, Verification Letter for Point Beach SLR Under Programmatic Biological Opinion for Northern Long-eared Bat NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2019-0002, Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2019-01-24024 January 2019 Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0045, Updated Final Response to NRC Generic Letter 2004-022017-12-29029 December 2017 Updated Final Response to NRC Generic Letter 2004-02 NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML17136A3222017-05-19019 May 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 ML17018A2712017-02-0909 February 2017 Flood Hazard Mitigation Strategies Assessment NRC 2016-0041, Submittal of 10 CFR 50.59 Summary Report for 20152016-08-31031 August 2016 Submittal of 10 CFR 50.59 Summary Report for 2015 NRC 2015-0072, Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan2015-12-16016 December 2015 Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan ML15300A1402015-11-0303 November 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15211A5932015-08-0303 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force NRC 2015-0043, Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 10072015-07-20020 July 2015 Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 1007 NRC 2014-0041, 10 CFR 50.59 Summary Report for 20132014-08-27027 August 2014 10 CFR 50.59 Summary Report for 2013 ML14147A0342014-06-0606 June 2014 Review of the 2013 Steam Generator Tube Inspections NRC 2014-0024, NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the F2014-03-31031 March 2014 NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukush ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 NRC 2013-0069, Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding2013-07-15015 July 2013 Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2013-0061, CFR 50.59 Summary Report for 20122013-06-28028 June 2013 CFR 50.59 Summary Report for 2012 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic NRC 2011-0059, 10 CFR 50.59 Summary Report for 20102011-07-0101 July 2011 10 CFR 50.59 Summary Report for 2010 2023-07-24
[Table view] Category:Technical
MONTHYEARL-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic ML14006A3192010-03-31031 March 2010 LTR-PAFM-10-50-NP, Rev. 0, Section XI Flaw Evaluation of Indication Recorded on RC-32-MRCL-ALL-03 of the Point Beach Unit 1 Inlet Nozzle to Pipe Weld. NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation2010-03-0303 March 2010 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation ML0935704152009-12-31031 December 2009 WEP-09-133 Np, Point Beach Unit 1 & Unit 2 (Wep/Wis) Extended Power Uprate License Amendment Request Responses to Request for Additional Information. ML0912505662009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Introduction Through Chapter 2, Section 2.5.7 ML0912505692009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Chapter 2, Section 2.5.8 Through Appendices ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822406862008-06-30030 June 2008 WCAP-16541-NP, Revision 2, Spent Fuel Pool Criticality Safety Analysis. NRC 2008-0029, Pressure and Temperature Limits Report2008-05-30030 May 2008 Pressure and Temperature Limits Report NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008 License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report2007-06-13013 June 2007 Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006 LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program NRC 2006-0054, Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis2006-06-0606 June 2006 Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis ML0600400192005-12-14014 December 2005 Westinghouse LTR-RCDA-873-NP Attachment Point Beach, Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature (Non-Proprietary) ML0533203122005-11-18018 November 2005 Reactor Vessel CMTRs (Non-Proprietary) NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure2005-09-0707 September 2005 Request for Withholding of Proprietary Information from Public Disclosure NRC 2005-0068, Submittal of Supporting Analyses Regarding Control of Heavy Loads2005-06-0303 June 2005 Submittal of Supporting Analyses Regarding Control of Heavy Loads ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0514002682004-10-0808 October 2004 Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material NRC 2004-0004, Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 20042004-08-30030 August 2004 Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 2004 NRC 2004-0081, Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 42004-08-13013 August 2004 Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 ML0426603132004-07-31031 July 2004 BAW-2467NP, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of Point Beach Units I and 2 for Extended Life Through 53 Effective Full Power Years. ML0508800622004-05-0707 May 2004 Licensee Procedure, HPIP 4.58, Issuance of Respiratory Equipment Revision 14 ML0508800432004-04-30030 April 2004 NMC Incident Response Team for Issues Encountered During Unit 1 Reduced Inventory and Nozzle Dam Installation at Pbnp 2022-07-29
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HPIP 4.40 TEDE ALARA EVALUATION DOCUMENT TYPE: Administrative REVISION: 0 EFFECTIVE DATE: February 6, 2002 APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Radiological Engineer OWNER GROUP: Radiation Protection
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POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ............... 3 2.0 DISCUSSION ............... 3 3.0 RESPONSIBILITIES ............... 4 4.0 PROCEDURE ............... 4
5.0 REFERENCES
............... 5 6.0 BASES ............... 5 Page 2 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION 1.0 PURPOSE 1.1 This procedure establishes the methods and practices to be used to perform a TEDE ALARA evaluation.
1.2 This procedure applies to all plant activities that generate airborne radioactivity.
2.0 DISCUSSION 2.1 Radiation protection practices have long emphasized avoiding unnecessary exposures.
This principle, now referred to as ALARA, means making every effort to maintain radiation dose as low as reasonably achievable. As a licensee of the NRC, we are required to implement a radiation protection program consisting of procedures and engineering controls to achieve occupational radiation dose that is ALARA.
2.2 When a specific ALARA evaluation is performed to justify the use or nonuse of respirators, the evaluation should consider the following:
2.2.1 The use of process and engineering controls, filtered ventilation systems and decontamination before the use of respiratory protection equipment; 2.2.2 Control of access, limitation of exposure time and the use of other types of exposure controls before the use of respiratory protection equipment; 2.2.3 The estimated benefit. The evaluation should show that the TEDE for the job will be ALARA, i.e., the internal dose avoided by using the respiratory protection equipment is likely to be greater than any additional external dose that may result from the use of respiratory protection equipment from respirator-induced inefficiency and other factors.
2.3 When application of engineering controls to keep radioactive material in air below values that constitute an Airborne Radioactivity Area is NOT practical, then other controls shall be implemented to maintain the total effective dose equivalent (TEDE) ALARA. The use of a respiratory device with a lower protection factor (PF) than the peak concentration may be selected to be consistent with TEDE ALARA 2.4 When the TEDE ALARA evaluation results do not show a clear, obvious indication of whether or not the use of a respirator is ALARA, professional judgment may be used as to whether or not to assign a respirator.
2.5 Terms used in this procedure:
ALARA - The operating principle of radiological protection that states that measures are to be implemented to keep radiation dose and intakes "as low as reasonably achievable."
Page 3 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION Total Effective Dose Equivalent, TEDE - The sum of the deep-dose equivalent (for external exposures) and the Committed Effective Dose Equivalent (for internal exposures).
Deep-Dose Equivalent, DDE - The dose equivalent at a tissue depth of 1 cm (1000 mg/cm2 ).
Dervived Air Concentration, DAC - The concentration of a given radionuclide in air, which, if breathed by the reference man for a working year of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> under conditions of light work, results in an intake of one ALI.
3.0 RESPONSIBILITIES None 4.0 PROCEDURE 4.1 A TEDE ALARA evaluation shall be done whenever the use of respiratory protection equipment is considered for the protection of personnel against airborne radioactive material or when the airborne contamination concentration will exceed 25 percent of a DAC. The evaluation should be documented using PBF-4230a.
NOTE: A TEDE ALARA evaluation does not need to be done before requiring the use of respiratory protection equipment as a precautionary measure when there is a large uncertainty about the magnitude of the projected concentrations of airborne radioactive material to which workers will be exposed (e.g., a new job with significant airborne contamination potential, but with no history of previous similar jobs). This is regardless of the magnitude of the projected external and internal dose.
4.2 To do the evaluation perform the following using PBF-4230a:
NOTE: For unknown mixtures of radionuclides, the PBNP specific DAC values, as given in HPIP 3.52, shall be used.
4.2.1 Describe the work to be performed. Highlight the work activities that may disturb contaminated surfaces and the manner by which the surfaces are disturbed. Include the time that the maximum exposed individual is expected to be in the area of concern. List expected dose rates, contamination levels and average ambient concentration of radioactive material in work place air (or the estimated average). The air concentration values should be expressed as fraction or percent of DAC. The values should be based on historical data or may be estimated using Tables 1 through 4 for beta/gamma contamination and Tables 5 through 8 for alpha contamination.
4.2.2 Describe the environmental conditions including elevated temperature and noise conditions and impacts on personnel safety.
Page 4 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION 4.2.3 Describe the process and engineering controls that will be used.
4.2.4 Describe the protective equipment and clothing, including the respirator, to be used and their effects on worker efficiency. Describe the comfort level of the worker regarding the use of the respirator.
4.2.5 Describe potential post-work negative impacts. Include the effects of personnel contaminations and skin dose assessments, portal monitor alarms, etc.
4.2.6 Calculate the dose that will be received not using respiratory protection equipment.
4.2.7 Calculate the dose that will be received using respiratory protection equipment. Respirator protection factors are listed in the legend at the bottom of Tables 1 through 8. If the impact of respirator protection equipment use on worker productivity is not known, assume that work time is increased by fifteen percent~l).
4.2.8 If the total dose using a respirator is less than or equal to the total dose not using a respirator, then the use of respiratory protection equipment is warranted. For instances where the above condition is not met, respirator use may still be warranted due to the benefits provided by nonradiological factors.
An example is the benefit of an air-supplied suit that provides cooling.
4.2.9 Complete the TEDE ALARA form and submit to RP Supervision for review.
4.3 Voluntary Use Respirators If the TEDE ALARA evaluation determines respiratory protection is not warranted, but the workers want some device, a dust mask (or filtering facepiece) may be used by the individual(s). Dust masks can be obtained at Ready Stores for this purpose.
5.0 REFERENCES
5.1 PBF-4230a, TEDE ALARA Evaluation 5.2 NP 4.2.1, ALARA Program 5.3 HPIP 4.57, Respirator Selection 6.0 BASES B-i Regulatory Guide 8.15, Acceptable Programs for Respiratory Protection, Revision 1, October 1999.
Page 5 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 1 Inspection Only - No Ongoing Work (walk-thru and/or visual examination only)
Potential Beta/Gamma Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dprn/100 sq. cm.) (mrad/h) Confined Area Normal Vent Neg. Flow Glovebox l.OOE+02 I1.OOE-03 0.000 0.000 0.000 0.000 2.50E+02 2.50E-03 0.000 0.000 0.000 0.000 5.OOE+02 5.OOE-03 0.000 0.000 0.000 0.000 I .OOE+03 I .OOE-02 0.000 0.000 0.000 0.000 2.50E+03 2.50E-02 0.001 0.000 0.000 0.000 5.OOE+03 5.OOE-02 0.001 0.000 0.000 0.000 1.00E+04 I.OOE-0 0.002 0.000 0.000 0.000 2.50E+04 2.50E-01 0.006 0.001 0.000 0.000 5.00E+04 5.00E-01 0.011 0.001 0.000 0.000 7.50E+04 7.50E-01 0.017 0.002 0.000 0.000 1.00E+05 I.00E+00 0.023 0.002 0.000 0.000 1.50E+05 1.50E+00 0.034 0.003 0.000 0.000 2.00E+05 2.00E+00 0.045 0.005 0.000 0.000 2.50E+05 2.50E+00 0.056 0.006 0.001 0.000 3.OOE+05 3.00E+00 0.068 0.007 0.001 0.000 4.00E+05 4.OOE+00 0.090 0.009 0.001 0.000 5.OOE+05 5.00E+00 0.113 0.011 0.001 0.000 7.50E+05 7.50E+00 0.169 0.017 0.002 0.000 1.00E+06 I .OOE+0 0.225 0.023 0.002 0.000 2.00E+06 2.OOE+01 0.450 0.045 0.005 0.000 3.OOE+06 3.OOE+01 0.675 0.068 0.007 0.001 5.00E+06 5.OOE+01 1.125 0.113 0.011 0.001 7.50E+06 7.50E+01 1.688 0.169 0.017 0.002 I .00E+07 I .OOE+02 2.250 0.225 0.023 0.002 2.00E+07 2.OOE+02 4.500 0.450 0.045 0.005 4.00E+07 4.OOE+02 9.000 0.900 0.090 0.009 6.00E+07 6.OOE+02 13.500 1.350 0.135 0.014 8.OOE+07 8.OOE+02 18.000 1.800 0.180 0.018 I.00E+08 1.OOE+03 22.500 2.250 0.225 0.023 2.OOE+08 2.OOE+03 45.000 4.500 0.450 0.045 Legend: < I DAC
> 1 DAC and < 50 DAC (PF Neg. Press. RespJPAPR = 50)
' -' "' ! is"', j';
-":- I,-...~ > 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> lOOODACand< IOO00DAC(PFSCBA= 10000)
,--, -, . " - - :- '. . -,- .. :1 P > 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page 6 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 2 Wet Decon/Routine Maintenance (wet surface wipedown, routine maintenance)
Potential Beta/Gamma Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mrad/h) Confined Area Normal Vent Neg. Flow Glovebox l.OOE+02 I.00-03 0.000 0.000 0.000 0.000 2.50E+02 2.50E-03 0.001 0.000 0.000 0.000 5.OOE+02 5.OOE-03 0.001 0.000 0.000 0.000 I.00E+03 1.00-02 0.002 0.000 0.000 0.000 2.50E+03 2.50E-02 0.006 0.001 0.000 0.000 5.OOE+03 5.00E-02 0.011 0.001 0.000 0.000 I.OOE+04 1.OOE-01 0.023 0.002 0.000 0.000 2.50E+04 2.50E-01 0.056 0.006 0.001 0.000 5.OOE+04 5.00E-01 0.113 0.011 0.001 0.000 7.50E+04 7.50E-01 0.169 0.017 0.002 0.000 I.00E+05 1.00E+00 0.225 0.023 0.002 0.000 1.SOE+05 I.SOE+00 0.338 0.034 0.003 0.000 2.OOE+05 2.00E+00 0.450 0.045 0.005 0.000 2.50E+05 2.50E+00 0.563 0.056 0.006 0.001 3.OOE+05 3.OOE+00 0.675 0.068 0.007 0.001 4.00E+05 4.00E+00 0.900 0.090 0.009 0.001 5.OOE+05 5.00E+00 1.125 0.113 0.011 0.001 7.50E+05 7.50E+00 1.688 0.169 0.017 0.002 I.OOE+06 1.00E+01 2.250 0.225 0.023 0.002 2.00E+06 2.00E+01 4.500 0.450 0.045 0.005 3.OOE+06 3.OOE+01 6.750 0.675 0.068 0.007 5.OOE+06 5.00E+01 11.250 1.125 0.113 0.011 7.50E+06 7.50E+01 16.875 1.688 0.169 0.017 I.00E+07 1.OOE+02 22.500 2.250 0.225 0.023 2.00E+07 2.00E+02 45.000 4.500 0.450 0.045 4.00E+07 4.00E+02 .!Ye/-90.000)l- 9.000 0.900 0.090 6.OOE+07 6.00E+02 st§gl35.000t',Jil 13.500 1.350 0.135 8.00E+07 8.00E+02 -5180.000 q io 18.000 1.800 0.180 1.00O+08 1.00E+03 225.000
,.& S 22.500 2.250 0.225 2.00E+08 2.00E+03 QA.4500000 ' 45.000 4.500 0.450 Legend: < I DAC
> I DAC and < 50 DAC (PF Neg. Press. RespJPAPR = 50)
-.' -, <. .=- - Y .3i,;,.
> 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
.¢ l.1 :,Ie
> 1000 DAC and < 10000 DAC (PF SCBA = 10000)
> 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page 7 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 3 Abrasive or Dry Surface Decon (sweeping, scrubbing)
Potential Beta/Gamma Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mradlh) Confined Area Normal Vent Neg. Flow Glovebox 1.OOE+02 I.OOE-03 0.002 0.000 0.000 0.000 2.50E+02 2.50E-03 0.006 0.001 0.000 0.000 5.OOE+02 5.OOE-03 0.011 0.001 0.000 0.000 1.00E+03 I .OOE-02 0.023 0.002 0.000 0.000 2.50E+03 2.50E-02 0.056 0.006 0.001 0.000 5.OOE+03 5.00E-02 0.113 0.011 0.001 0.000 I .OOE+04 1.OOE-01 0.225 0.023 0.002 0.000 2.50E+04 2.50E-01 0.563 0.056 0.006 0.001 5.00E+04 5.00E-01 1.125 0.113 0.011 0.001 7.50E+04 7.50E-01 1.688 0.169 0.017 0.002 1.00E+05 1.OOE+00 2.250 0.225 0.023 0.002 1.50E+05 1.50E+00 3.375 0.338 0.034 0.003 2.00E+05 2.00E+00 4.500 0.450 0.045 0.005 2.50E+05 2.50E1+00 5.625 0.563 0.056 0.006 3.00E+05 3.00E+00 6.750 0.675 0.068 0.007 4.00E+05 4.00E+00 9.000 0.900 0.090 0.009 5.00E+05 5.00E+00 11.250 1.125 0.113 0.011 7.50E+05 7.50E+00 16.875 1.688 0.169 0.017 1.00E+06 1.OOE+01 22.500 2.250 0.225 0.023 2.00E+06 2.00E+01 45.000 4.500 0.450 0.045 3.00E+06 3.00E+01 rg67:500>, A> 6.750 0.675 0.068 5.00E+06 5.00E+01 t~U12t,0Q-4, 11.250 1.125 0.113 7.50E+06 7.50E+01l t 8*750j*' 16.875 1.688 0.169 1.OOE+07 .OOE+02 25.000 22.500 2.250 0.225 2.00E+07 2.00E+02 f :#*5.,000.°'* 45.000 4.500 0.450 4.OOE+07 4.00E+02 .00.0001, A 90.000 , 9.000 0.900 6.OOE+07 6.OOE+02 - '.1350.000 '135.000 , 13.500 1.350 8.OOE+07 8.OOE+02 1800.000 - J80.000 18.000 1.800 11.OOE+08 1.00E+03 :2250.000 ,.-225.000O, -' 22.500 2.250 2.00E+08 2.00E+03 '4500.000 , i/450.000!P' 45.000 4.500 Legend: < 1 DAC
> I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
> 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> 1000 DAC and < 10000 DAC (PF SCBA = 10000)
> 10000 DAC (>PF of Resp. Protection; Special Considerations) i -
Page 8 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 4 Grinding/Welding (aggressive mechanical disturbance)
Potential Beta/Gamma Airborne Hazard as a Function of Working Enironment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mrad/h) Confined Area Normal Vent Neg. Flow Glovebox 1.OOE+02 I1.OOE-03 0.225 0.023 0.002 0.000 2.50E+02 2.50E-03 0.563 0.056 0.006 0.001 5.OOE+02 5.00E-03 1.125 0.113 0.011 0.001 I1.OOE+03 I.OOE-02 2.250 0.225 0.023 0.002 2.50E+03 2.50E-02 5.625 0.563 0.056 0.006 5.00E+03 5.00E-02 11.250 1.125 0.113 0.011 I.OOE+04 I.00E-0 22.500 2.250 0.225 0.023 2.50E+04 2.50E-0 1 56.250: 'A, 5.625 0.563 0.056 5.00E+04 5.00E-01 . 12. 500'. 11.250 1.125 0.113 7.50E+04 7.50E-01 -168.750?:... 16.875 1.688 0.169 I.00E+05 I.00OE+00 :,25 22.500 2.250 0.225 1.50OE+05 1.50E3+00 33.750 3.375 0.338 2.00E+05 2.00E+00 .i
- - 45.000 4.500 0.450 2.50E+05 2.50E+00 i456230 X p 56 25QA': 5.625 0.563 3.00E+05 3.00E+00 IL-67550ttivA T 6.750 0.675 4.00E+05 4.00E+00 94900'QQ0,'7' 90000i t 9.000 0.900 5.00E+05 5.00E3+00 1125 '...112.500.' 11.250
. 1.125 7.50E+05 7.50E+00 -'1687.5 . -168350Qt23`iI 16.875 1.688 1.OOE+06 1.00E+01 - 2250": ;. 225:000k-Kt. 22.500 2.250 2.00E+06 2.00E+01 4500' .: 450:J 45.000 4.500 3.00E+06 3.OOE+01 :.6750 '. '675:000'f- -67;500,,*;2, 6.750 5.OOE+06 5.OOE+01 12Sjaii . 1125' - 1I2e5O0dg 11.250 7.50E+06 7.501E+01 6~~5~ 1687.5 ' ~1.7 1.OOE+07 I.00E+02 . % - 2250 . ' 225;000,. 22.500 2.00E+07 2.00E+02 - 4500 . . 450.000t,
'00090 45.000 4.00E+07 4.00E+02 ^,,90000 :,- ;: 9000 - ' -: ^900.000Et 2Tv90000.oo-6.00E+07 6.00E+02 .. 3500 jJ 1350 : 35.00!-..,
1/2.4135000$¢ 8.00E+07 8.00E+02 x180000,;.:; "-180009>-- 1800 _1 8 0.0001._._,
I.OOE+08 1.OOE+03 ,,-,y-225000;t. rj 22500,;. 2250 .; f225.000js 2.00E+08 2.OOE+03 -'450000'"z, ^i' 45000 T.. 4500 - 450.000 S.
Legend: < I DAC
> I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
-. - '), , I.,-4, ;-.-, .1-
"". , -!. . , > 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> 1000 DAC and < I0000 DAC (PF SCBA = 10000)
> 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page 9 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLES Inspection Only - No Ongoing Work (walk-thru and/or visual examination only)
Potential Alpha Airborne Hazard as a Function or Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/IOO sq. cm.) (mrad/h) Confined Area Normal Vent Neg. Flow Glovebox l.00E+02 L.OOE-03 0.015 0.002 0.000 0.000 2.50E+02 2.50E-03 0.038 0.004 0.000 0.000 5.OOE+02 5.OOE-03 0.075 0.008 0.001 0.000 1.OOE+03 L.OOE-02 0.150 0.015 0.002 0.000 2.50E+03 2.50E-02 0.375 0.038 0.004 0.000 5.OOE+03 5.OOE-02 0.750 0.075 0.008 0.001 1.OOE+04 L.OOE-01 1.500 0.150 0.015 0.002 2.50E+04 2.50E-01 3.750 0.375 0.038 0.004 5.OOE+04 5.OOE-01 7.500 0.750 0.075 0.008 7.50E+04 7.50E-01 11.25 1.125 0.113 0.011 1.00E+05 1.OOE+00 15 1.500 0.150 0.015 1.50E+05 1.50E+00 23 2.250 0.225 0.023 2.00E+05 2.OOE+00 30 3.000 0.300 0.030 2.50E+05 2.50E+00 38 3.750 0.375 0.038 3.OOE+05 3.OOE+00 45 4.500 0.450 0.045 4.00E+05 4.OOE+00 6.000 0.600 0.060 5.OOE+05 5.OOE+00 7.500 0.750 0.075 7.50E+05 7.50E+OO 11.25 1.125 0.113 1.00E+06 1.00E+01 _ _ 15 _ _ 1.500 0.150 2.00E+06 2.00E+01 30 3.000 0.300 3.OOE+06 3.OOE+01 Q45 4.500 0.450 5.OOE+06 5.OOE+01 , 7.500 0.750 7.50E+06 7.50E+01 1125:. -, iS~'I .}. 11.25 1.125 1.OOE+07 I.00E+02 - .1500 '-'- 15 1.500 2.OOE+07 2.OOE+02 ,3000 -*.300'. 1 $W: 30 3.3 4.00E+07 4.00E+02 : SSl60Qi~rs A60~, 666000 6.OOE+07 6.OOE+02 ' 9000 - ' .900 , $: '- .. 9QS . 9 8.OOE+07 8.OOE+02 120000 W§.' 1200 120Jii-i 12 l.OOE+08 1.00E+03 13000- 1500 : 8 '15 2.00E+08 2.00E+03 k;0000 iZ 3000 - - 300) -:1 30 Legend: < 1 DAC
> I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
> 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> 1000 DAC and < I0000 DAC (PF SCBA = 10000)
--V. > 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page IOof 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 6 Wet Decon/Routine Maintenance (wet surface wipedown, routine maintenance)
Potential Alpha Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mradlh) Confined Area Normal Vent Neg. Flow Glovebox 1.OOE+02 I.OOE-03 0.150 0.015 0.002 0.000 2.50E+02 2.50E-03 0.375 0.038 0.004 0.000 5.OOE+02 5.OOE-03 0.750 0.075 0.008 0.001 1.OOE+03 I.OOE-02 1.500 0.150 0.015 0.002 2.50E+03 2.50E-02 3.750 0.375 0.038 0.004 5.OOE+03 5.OOE-02 7.500 0.750 0.075 0.008 1.OOE+04 l.OOE-01 15 1.500 0.150 0.015 2.50E+04 2.50E-01 38 3.750 0.375 0.038 5.00E+04 5.00E-01 t:s~751;U- 7.500 0.750 0.075 7.50E+04 7.50E-01 13 11.25 1.125 0.113 l.00E+05 1.OOE+00 ____________ 15 1.500 0.150 l.50E+05 l.50E+OO W-259 W 23 2.250 0.225 2.00E+05 2.00E+OO ____MM 30 3.000 0.300 2.50E+05 2.50E+00 _____________ 38 3.750 0.375 3.OOE+05 3.OOE+00 8lIjI50 45 4.500 0.450 4.OOE+05 4.00E+00 " fi.y60 K; 6.000 0.600 5.OOE+05 5.OOE+00 Q50$X i 975I2 '> 7.500 0.750 7.50E+05 7.50E+00 - 1125 . r'j13w 11.25 1.125 1.00E+06 1.00E+0 -`i1500 '515ff< 15 1.500 2.00E+06 2.OOE+01 - 3000 - 30(f 30 3.000 3.00E+06 3.OOE+01 4500 ' t 45p- 9 45 4.500 5.00E+06 5.0oE+01 '7500 > :5iW:?. 7.500 7.50E+06 7.50E+01 #1tJJap 25Q 1125, ' 1i3.23 11.25 1.00E+07 l_.OOE+02
___-_.__ _ l ', '- 1500 'i.50.*i>pZ 15 2.00E+07 2.OOE+02 , 3000 ' 30 4.00E+07 4.00E+02 _ 600, 1607 0-
6.00E+07 6.00E+02 .00< it: 9000 ; 9 &y, 90 8.00E+07 8.00E+02 . MPi20, 1200Q 1,
-1200 120 1.00E+08 1.OOE+03 £0 it15000'4 0 < 1500 150 2.00E+08 2.00E+03 ' 0040 3000 C'
'300W
> I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
I -Ze n'.-. ". ,i f t- ,
> 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> 1000DACand < 10000 DAC(PFSCBA = 10000)
> 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page I I of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 7 Abrasive or Dry Surface Decon (sweeping, scrubbing)
Potential Alpha Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mrad/lh) Confined Area Normal Vent Neg. Flow Glovebox 1.OOE+02 EOOE-03 1.500 0.150 0.015 0.002 2.50E+02 2.50E-03 3.750 0.375 0.038 0.004 5.OOE+02 5.OOE-03 7.500 0.750 0.075 0.008 1.OOE+03 EOOE-02 15 1.500 0.150 0.015 2.50E+03 2.50E-02 37 3.750 0.375 0.038 5.OOE+03 5.OOE-02 ; '75 4" 7 500 0.750 0.075 1.OOE+04 I.OOE-01 :?Is ^'150 15 1.500 0.150 2.50E+04 2.50E-01 38 3.750 0375 35375 5.OOE+04 5.OOE-.01 ' 750'4 ' '>;'.75>5 g I 7.500 0.750 7.50E+04 7.50E-01 ' 1125 J:Ž'113,A#2i 11.250 1.125 1.OOE+05 1.00E+00 -I;_1500- ;. if 0 15 1.500 1.50E+05 1.50E+00 : -. 2250 t 25, *i 23 2.250 2.OOE+05 2.00E+00 3000 .- 900L-r t 30 3.000 2.50E+05 2.50E+00 . -3750 , 3J5 M, 38 3.750 3.OOE+05 3.00E+00 '. l4500 t.-%50 45 4.500 4.00E+05 4.00E+00 6000 . g ;*
.i S Q60.AY> 6.000 5.OOE+05 5.00E+00 ;-7500 - 750k1 3. :'~75C5< ; 7.500 7.50E+05 7.50E+00 1125,. 1 11.250 1.OOE+06 1.00E+01 :1500
-j.Q00t2' ;150),' 15 2.OOE+06 2.OOE+01 'Z;t sO0QO-' - 3000 ;2-}300 n&.§ 30 3.OOE+06 3.00E+01 .4500 .(45Q00. :- 45 5.OOE+06 5.00E+01 *A 05-Q0' . 7500 - .75O,?$.si: ('.5J.:;,
7.50E+06 7.50E+01 :s5afgcotFXXi
-1125 --uzrr.gB~.,
ttS§ ........
1.OOE+07 1.00E+02 50000, 'i'1&000 ' - 1500 ' 50022t 2.OOE+07 2.00E+02 1 O00,000 -3P03000
' -300<.S-4.00E+07 4.00E+02 ' 00000i3.1x, ':6O3 ' 6000 '600 ,t, 6.OOE+07 6.00E+02 ' 00000P:K. 900 00' . l 9000 __________; __
8.OOE+07 8.OOE+02 1t200000
'120000!,. 12000Y.i j4i'.b 1200 1.00E+08 1.00E+03 ' 500000:+>iZ- 150000 A?~ 1500 2.00E+08 2.00E+03 j,.30Q00 '$3000'OO, . 3)Q M'. 3000 Legend: <1 DAC
> I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
- r. , " . '- .;. ., r ' .' ,4 1;-' ' .' ' : . .- I.' . 4'-
- t. , , -, -"IIi' >50 DAC and < 1000 DAC (PFAirline/Hood = 1000)
> IOOODAC and < I0000 DAC (PF SCBA= I0000)
> 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page 12 of 13 INFORMATION USE
POINT BEACH NUCLEAR PLANT HPIP 4.40 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 0 February 6, 2002 TEDE ALARA EVALUATION TABLE 8 Grinding/Welding (aggressive mechanical disturbance)
Potential Alpha Airborne Hazard as a Function of Working Environment Loose Surface Contamination (LSC) Effective DAC Fraction (dpm/100 sq. cm.) (mrad/h) Confined Area Normal Vent Neg. Flow Glovebox 1.00E+02 I .OOE-03 iJX:50 91 5 2 0 2.50E+02 2.50E-03 -Ž:375A.2s; 38 4 0 5.OOE+02 5.OOE-03 ;j'75O,.2 . 7 . 8 1 1.00E+03 l .OOE-02 1500 5 hO;-. - , .. 1500 2 2.5013+03 2.50E_
___750____38 2 1.0013+04 1.0023-01 K 150O.;'j'15 1500 : 15 2.50E+04 2.50E-01 : : '375'; v 383750 5.OOE+04 5.OOE-01 41 - 7500 . £i 0,s750 " ' -75 ty 7.50E+04 7.50E-01 I 125 ->X1 00-1I.OOE+OS IE l - ;,5 1.50E+05 I.SOE+O" 2.00E+05 2.OOE+00 -3000.
2.50E+05 2.50E+00 IM250 3750 -
3.00E+05 3.00E+00 ,Q ) . 4500 4.OOE+05 4.00E+00 - S- 6000 --600. *-'-6()0.
5.00E+05 5.00E+OO w A.5QOO 7500 :
7.50E+05 7.50E2+00 z } 50t3 1125-1.00E+06 1.OOE+01 j05Q93MAN W915QD)00J ; :- -1500 2.OOE+06 2.00E+01 A9IP0 A3Q09 ; 3000 M30XQ 3.00E+06 3.00E+01 t 45Q _0)W a' W45W)0Qf -l 50Q0 4500.-
5.00E+06 5.00E+01 50Qi 75-07 R 755X0. -7500 -
7.50E+06 7.50E+01 M1I5Q
.L100 "25AQ)OM K112509,0, 1.00E+07 1.00E+02 W1550w00OOJR fo 50 a0 u i00 -:150 'O 2.00E+07 2.00E+02 3000:
O'01 NW - -ooOO; 4.00E+07 4.00E+02 .* ;, 60000Q00Q)V4 t'6OO00014 0 k :60COOO : 600009ke .
6.00E+07 6.00E+02 .N'-9..00o000'.2 900oO -900000' . 900000 s .o§,
8.00E+07 8.00E+02 -. 1 i 112000000f.!1 120000000WiW. t':j: 120000 5 1.00E+08 1.00E+03 EN 5000000QL 2 ;1500Q00TO -r,15 J ) : i)50000, -r 2.00E+08 2.OOE+03 ?; 30000000(O eF7 300000OO " '3000000% , ij.300000*..
Legend: I DAC
>I DAC and < 50 DAC (PF Neg. Press. Resp./PAPR = 50)
I - " 1- -,, -',.,
'Tt": - ",
- ..j , " > 50 DAC and < 1000 DAC (PF Airline/Hood = 1000)
> 000 DAC and< I0000 DAC (PFSCBA= 10000) 1.:,I V i -, , . " " -C4 > 10000 DAC (>PF of Resp. Protection; Special Considerations)
Page 13 of 13 INFORMATION USE