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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 4.58 ISSUANCE OF RESPIRATORY EQUIPM ENT DOCU;N ENT TYP E: Administra tive REVIS ION: 13 EFF EC1 rIVE DATE: March 19,2004 APPROVAL Al JT1IOR ITY: Department Manager PROCEDURE ONVNE R (title): Respiratory Protection Coordinator OnVNI ER GROUP: Industrial Health & Safety 9-1
POINT BEACH NUCLEAR PLANT HPIP 4.58 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 13 March 19, 2004 ISSUANCE OF RESPIRATORY EQUIPMENT 1.0 PURPOSE 1.1 This procedure is to provide guidance in the useand issuanceof respiratory equipment.
1.2 This procedure implements the requirements of the Americ an National Standards Institute Z88.2 1992, and is designed to maintain respirator program efficiency, ensure proper respirators are issued to personnel requirin g respiratory protection, and provide a documented record of program activitie s.
1.3 This procedure does NO T cover the issue of respiratory equipment for emergency use.
Emergent use equipment is covered in HP 4.7.
2.0 DISCUSSION 2.1 The issueof improper respiratory protection may provide reducedor non-existentlevels of personal protection or may even be worse than no respiratory protection at all.
2.2 Only trained Radiation Protection personnel shall issue respirators accordance with this procedure.
2.3 Each respirator user shall sign the Respirator Issue Record, PBF-4234, indi cating:
2.3.1 Receipt of the respirator.
2.3.2 That the user understands and agrees to compl y with all of the respiratory program requirements.
3.0 RESPONSIBILI TIES 3.1 The Respiratory Protection Program Administrator - Responsible for administering and overseeing the respiratory protection program and for conducting the required evaluations of the program. The Site Industrial Health and Safety Manager shall assumeoverall responsibility of Program Administrator.
3.2 PBNP Respiratory Protection Coordinator - Implements the Respiratory Protection Program, to include development of site-specific proceduresand provisions.
3.3 Radiation Protection Organization - Issuarce of approved respiratory protection to qualified individuals.
3.4 Respirator Users - It is the responsibilit y of personnel authorized to use respiratory protection equipment to use such equipment in accordance with this procedure and training received.
Page 2 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP4.58 HEA LTH PHYS ICS IMPLEMENT ING PROCEDURES Revision 13 March 19, 2004 ISSUANCE OF RESPIRATORY EQUIPMENT 4.0 PROCEDURE 4.1 For Issueof Tight Fitting Facepieces IssuerShall:
4.1.1 Verif y respirator user approval requirements:
- a. Successful completion of a medical evaluation.
- b. Successful completion of respirator wearer training within the last 12 months.
- c. Successful completion of a respirator fit test within the last 12 months.
NOTE: If the MIatrix Is unavall able, or cannot be upda ted for any reason, verify the Indivi dual's status with Dosimetry personne l/
In additio n, the latest printed quali fication report may be updat ed manually to reflect the Individ ual's status.
Respirator use approval Is indicated by lookin g up an individual's status on either the o latest printed qualific atio n report, OR o on-line respirator qualifica tion matrix.
4.1.2 For non-radiological (personnel safety) issuesverify that a respirator selection checklist (RSC) hasbeencompleted for thespecificjob for which the respirator will be issued and that the worker understands the requirements of the RSC. The Respirator Issue Record (PBF-4234) is required to be with theappropriateRSCin thelssuePoint lssueLog.
NOTE: IF either4.13a or 4.13b are NOT met, DO NOT issue a respirator until both conditions are satisfied.
4.1.3 Respirator IssueCriteria
- a. Verify that the respirator useris deanshaven in thesealareaof the respirator, and that no hair protrudes into the facepiecethat can interfere with therespirator'sworking parts.
- b. If corrective lensesare required for vision correction by the user (as determine through the online matrix or printed report), then the user shall have the corrective lens insert kit with them at the time of issue unless soft contact lensesare being worn. (B-3)
Page 3 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP4.58 HEA LTH PHYS ICS I M PL EMENT I N G PROCEDURES Revision 13 March 19, 2004 ISSUANCE OF RESPIRATORY EQUIPMENT 4.1.4 Verif y the respirator is ready for issue:
- a. Respirator is in a seaed plasic bag.
- b. Respirator inspection due date has NOT expired on the Respiratory Protection Equipment Inspection (Label), PBF-4232.
4.1.5 If required, issue negative pressure filters or canisters in accordance with respiratory sdection checklist or RWP.
4.1.6 Ensure that all filters, cartridg es and canisters used are labeled and color coded with the NIOSH approval label, and that the label is NOT removed and is legible (s.1).
4.1.7 Complete the following portions of the Respirator IssueRecord, PBF-4234, attached to the issuepoint copy of the applicable RWP or RSC.
- a. Issuedate
- b. Issued by (legibl y printed technicians initia Is) 4.2 Complete Step 4.3 for tight fitting facepiece issue, Step 4.4 for powered air purifying respirator issue. Step 4.5 for an air-supplied bubble hood respirator issue, or Step 4.6 for a ful I -fa ce air supplied mask issue.
NOTE: The user shall complete all required Inspections and checks at the issue point prior to being Issued the respirato r. The completion of this activity is docum ented on PBF-4234, "Respirator Issue Record." (B.)
4.3 Tight Fitting Facepieces 4.3.1 User shall inspect the respirator.
- a. Check the condition of the facepiece and headbands for deterioration of the rubber.
- b. Inspect the seat area of the facepiece for evidence of distortion and deterioration.
- c. Inspectthelens ring for defectsand verify thering is holding the lens securely in place.
- d. Inspect the cartridge reoeptacles for cracks, nicks, and damaged threads.
Page 4 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP 4.58 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 13 March 19, 2004 ISSUANCE OF RESPIRATORY EQUIPMENT
- e. Verify the cartridge gaskets are free of cracks and nicks.
- f. Vi suafly inspectthe inhalation valves and verify that they are attached to the post on the inhalation valve seat
- g. Remove the exhalation valve cover and inspect the flaps. (8.4)
- h. Check all fitting sand connections for tightness.
- i. Check the facepiece lens for clarit y. Lens should NOT be scratched to the point of affecting visi bilit y or otherwise damaged.
- j. Install vision correction lens insert kit if required by the user for normal vision. (8.3) 4.3.2 User shall functionall y test the respirator.
- a. Don the respirator.
- b. Breathe normall y to verif y proper operation of the inhalation and exhalation valves. Valves should NOT stick.
- c. Perform positive and negative pressure check (leak check) in accordance with Step 4.3.3 and 4.3.4.
4.3.3 Positive pressurecheck
- a. Close off the exhalation valve by sealing the palm of a hand against the exhalation valve cover and exhale gentl y into the facepiece.
- b. The face fit is considered satisfactory if a slight positive pressurecan be built up inside the facepieceand held for 10 seconds without any evidence of outward Ieakage of air at the seal 4.3.4 Negative pressurecheck
- a. The design of the inlet opening of some cartridges can NOT be effectivel y covered with the palm of the hand.
- b. The test can be performed by coverin g the inlet opening of the cartrid ge with a thin latex or nitrile glove.
- c. Close off the inlet opening of the canister or cartri dges by coverin g with the palm of the hands or by replacing the filte r seals.
- d. Inhale gently so that the facepiece collapsesslightly, and hold the breat for 10 seconds.
Page 5 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP4.58 HEA LTH PHYS ICS IMPLEMENT ING PROCEDURES Revision 13 March 19. 2004 ISSUANCE OF RESPIRATORY EQUIPMENT
- e. If the facepiece remains I n its slig htl y colla psed condition and no inwa rd leakage of air is detected, the tightnessof the respirator is considered satisfactory.
4.3.5 Complete the following portions of the Respirator IssueRecord, PBF-4234.
- a. Respirator FacepieceNumber (from facepiece tag)
- b. Size(Type of mask
- c. Inspection due date
- d. Wearers name (printed) 4.4 MSA Powered Air Purifi er Respirator (PAPR)
NOTE: If batte ry or blow er rails during use, the wearer will still be able to breath through the filter. Ir filters beco me clogged, remove the enti re facepie ce or discon nect the breathing tube and exit the area in a calm manner.
Report any respirator failure to Radiation Protection person net.
Complete PBF-4236.
4.4.1 Visuall y inspect all equipment for indication of damage or deterioration.
4.4.2 Ensure gasket is in place on respirator intak e connection.
4.4.3 Connect hose to magnehelix.
4.4.4 Turn on blower switch and verif y blower operation and flow rate to be approximately 4 CFM or 115 LPM.
4.4.5 Mount batter y/blow er assembly on belt and don belt.
4.4.6 Turn on blower and connect breathing tube to mask.
4.4.7 Check for cross-threaded connections by grasping the mask front and twisting the hose to insure it will stay attached. The unit is now ready for use 4.4.8 Log blow er and battery ID numbers under applicable columns on issue log.
Page6 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP 4.58 HEA LTH PHYS ICS I M PLEMENT ING PROCEDURES Revision 13 March 19 2004 ISSUANCE OF RESPIRATORY EQUIPMENT 4.5 Bubble Hood (Radiological Use Onl y)
NOTE: Bubb le hood users are NOT required to have a fit test to wear the hood, however, they SIIALL have medical clearan ce and appropriate training.
NOTE: Radiation Protection personnel will perrorm the steps outlined below and provide assistance to individ uals using air supplied respiratory equipment as needed.
4.5.1 Verif y that the air supply to be used with the bubble hood has been tested in accordance with, and met the requirements of HPIP 4.56. Testing Supplied Air for Air -line Respiratory Equipment.
4.5.2 Check the blue supply air hose. Bullard airline filter (if used), manifold and regulated air hoses for proper installation and ensure that all Chicago fitting s are lock wi red or pinned to prevent accidental separation of the connection.
Verif y that the air supply pressuregauge is in current calibration and then turn on the air supply to the manifold (if off ).
NOTE: A shelf lire or three (3) years is recommen ded as a safety precau tion; however, this is NOT mandatory If a visual inspection is made or all components and found to be satisfactory prior to putting the respirators in service.
4.5.3 Inspectall bubble hoods for material softness.darity, cracks and seam strength.
4.5.4 Place air distribution unit into the hood and snap retainers around the unit if required. Inspect hood material integrity to ensure that the hood is in operating condition.
4.5.5 Log the issueof the bubble hood on PBF-4234 attached to the appropriate RWP by filling in the Date, writing B ubblehood" in the "Other Equipment' column, and filling in the Issuer and Wearer Name and Signature columns.
4.5.6 Connect the air line fitting s and establish air flow to the hood.
Page 7 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP4.58 HEALTH PHYSICS IMPLEMENT ING PROCEDURES Revision 13 March 19, 2004 ISSUANCE OF RESPIRATORY EQUIPMENT NOTE: The following data Is only applic able to the Nucle ar Power Outfitte rs hood NIOSII certi fication . Use of other manufactu rer's hood or other air line length requires approval of the Respirator y Protection Coordinator and strict compliance with the appropriate NIOSII hood certification.
4.5.7 Adjust air supply pressure so that air flow is between 6 and 15 cubic feet per minute. For an air line length of 50 feet, a pressuie range of 20 to 28 psig corresponds to a flow rate range of 6 to 15 cfm.
4.5.8 Put on the outer protectiv e clothing garment.
4.5.9 Place hood over the indiv Idual's head, setting the lower edge at the shoulders.
Tuck the inner plastic cape inside of the outer protective clothing garment.
4.5.10 Smooth the outer cape against the outside of the upper outer garment.
4.5.11 Tape outer cape to outer protective dothin g.
4.5.12 Tig hten belt over outer cape and connect the air line to the belt.
4.5.13 Assure adequate freedom of movement by extending and bendin g the arms.
Adjust the hood, if necessary. Run the air line from the belt around the shoulder to the hood. Secure the belt and air line with tape.
4.5.14 Verif y that the pressureis within the required pressurerange (20-28 psig),
adjust if necessay. In general, higher flow provid es a higher protection factor.
4.5.15 Document air system PBNP equipment serial numbers and air supply pressure verification on Form PBF-4107a, and periodically check to insure pressue remains constant.
4.5.16 SeeNP 4.2.32 for standby rescueperson(s) requirements. (s.s) 4.6 Supplied Air Respirator- Full Facepiece (Radiological or Chemical Use)
NOTE: Radiation Protection personnel will perform the steps outlined below and provide assistance to Individ uals using air supplied respiratory equipment as needed.
4.6.1 Verif y that the air supply to be used with the supplied air hood system has been tested in accordance with, and met the requirements of, HPIP 4.56, Testing Supplied Air for Air -line Respiratory Equipment.
Page 8 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP4.58 HEALTH PHYSICS IMPLEMENTING PROCEDURES Revision 13 March 19, 2004 ISSUANCE OFRESPIRATORY EQUIPMENT 4.6.2 Check the blue supply air hose, Bullard airline filter (if used), manifold and regulated air hoses for proper installa tion and ensure that all Chicago fitting s are lock wi red or pinned to prevent accidental separation of the connection.
Verif y that the air supply pressuregauge is in current calibration and then turn on the air supply to the manifold (if off).
4.6.3 Verif y that the user has inspected the facepiece as required in Step 4.3 above.
4.6.4 Inspect the hoseand pressure regulator block to insure all connections are tight and that no cracking or degradation of the hose exists.
4.6.5 Connect the supply hose to the mask and dip the regulator block onto a belt.
4.6.6 Log the Issue of the airli ne respirator on PBF-4234 attached to the appropri ate RWP by filling in the Date, Respirator Mask Number Size/Type, Inspection Due Date, logging the Breathing Tube and Regulator Block number is the Other Equipment' column, and filling in the Issuer and Wearer Name and Signature columns.
CAUTION' Take care NOT to contam Inat e the supplie d air hose quic k disc on nects.
4.6.7 Connect the air line fitting s and establish air flow to the facepiece.
4.6.8 Adjust air supply pressue so that air flow is between 4 and 6 cubic feet per minute. For an air line length of 50 feet, a pressure range of 10 to 15 psig corresponds to a flow rate range of 4 to 6 cfm.
4.6.9 Verif y that the pressureis within the required pressurerange (10-15 psig),
adjust if necessay. In general, higher flow provid es a higher protection factor.
4.6.10 Document air system PBNP equipment serial numbers and air supply pressire verification on Form PBF-4107a, and periodically check to insure pressute remains constant.
4.6.11 SeeNP 4.2.32 for standby rescue person(s) requirements. (B85) 4.7 User shall sign the Respirator IssueRecord, PBF-4234, (if not already done so) indicatin g receipt of a functional respirator, use of any required corrective I enses, and compl iance with the appropriate RW P or RSC.
4.8 Remind the worker to recheck the seal at the work site (if taking it to another site) and to placethe respirator in the proper location fol lowi ng use of i t.
Page9 of 10 INFORMAT ION USE
POINT BEACH NUCLEAR PLANT HPIP 4.58 HEALTH PHYS ICS IMPLEMENT ING PROCEDURES Revision 13 March 19. 2004 ISSUANCE OF RESPIRATORY EQUIPMENT
5.0 REFERENCES
5.1 American National StandardsInstitute, ANSI Z88.2, Respiratory Protection 5.2 Department of Labor Occupational Safety and Health Administration, 29 CFR 1910.134, Respiratory Protection 5.3 Nuclear Regulatory Commission, 10 CFR 20 Subpart H, Respiratory Protection 5.4 NUREG/CR-0041, Manual of Respirator y Protection 5.5 NP 4.2.32, Respiratory Protection Program 5.6 HP 4.7. Emergency Responsewith Respiratory Equipment 5.7 HPIP 4.56. Testing Supplied Air for Air -line Respiratory Equipment 5.8 PBF-4107a, Bubble Hood Air Supply Pressure Record 5.9 PBF-4231, Respirator Sdection Checklist 5.10 PBF-4232, Respiratory Protection Equipment Inspection (Label) 5.11 PBF-4234, Respirator Issue Record 5.12 PBF-4236, Respiratory Protection Device Failure Report 6.0 BASES B-1 CAP027696 (QCR 97-0069), Report Used to Veri fy Eli gibilit y for Respirator Use/Issue ListsSomePersonnelWithout a Medical StatusReview Within the LastYear B-2 CAP014109 (CR 01-2050), LessThan Adequate Respirator Issuarre B-3 CAP031029, Vision Correction for Respiratory Equipment B-4 CAP0346221CA032663/ PCR054284, Improvement to Respiratory Protection Program (Item #12)
B-5 CAP051358/PCR054274, Training Materials Not in Compliance with 10CFR20.1703(f)
Page 10 of 10 INFORMAT ION USE