Letter Sequence Request |
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EPID:L-2019-LLQ-0003, Request for Approval of Change to Quality Assurance Topical Report (Approved, Closed) |
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Request for Approval of Change to Quality Assurance Topical ReportML19339E544 |
Person / Time |
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Site: |
Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, 07201036 |
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Issue date: |
12/05/2019 |
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From: |
Simpson P Exelon Generation Co |
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To: |
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
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References |
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RS-19-075 |
Download: ML19339E544 (16) |
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Similar Documents at Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, 07201036 |
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors 2024-01-03
[Table view] Category:Quality Assurance Program
MONTHYEARRS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 ML22111A2152022-03-31031 March 2022 2 to Updated Safety Analysis Report, Chapter 17, Quality Assurance JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 ML21257A2532021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 1, Appendix 1A, Quality Assurance Program for Design and Construction, List of Effective Pages ML21179A0462021-06-21021 June 2021 4 to Final Safety Analysis Report, Chapter 17, Quality Assurance NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML21008A3942020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance JAFP-20-0006, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102020-02-10010 February 2020 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 ML19350A8302020-01-0909 January 2020 Review of QA Program Changes RS-19-075, Request for Approval of Change to Quality Assurance Topical Report2019-12-0505 December 2019 Request for Approval of Change to Quality Assurance Topical Report JAFP-19-0016, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102019-02-0808 February 2019 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018 Summary of Changes to Quality Assurance Topical Report, NO-AA-10 RA-16-007, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, Revision 88, 89 and 902016-02-0808 February 2016 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, Revision 88, 89 and 90 CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual ML14353A2672014-12-15015 December 2014 Summary of Changes to the Constellation Energy Nuclear Group LLC Quality Assurance Topical Report RA-14-010, Summary of Changes to Exelon Generation Company,Llc, Quality Assurance Topical Report, NO-AA-102014-02-0606 February 2014 Summary of Changes to Exelon Generation Company,Llc, Quality Assurance Topical Report, NO-AA-10 CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G RA-12-006, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-102012-02-0606 February 2012 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10 ML12011A0872011-12-16016 December 2011 ISFSI & Nine Mile Point, and R. E. Ginna, ISFSI - Quality Assurance Topical Report, Revision 6 CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications ML12011A1242011-12-0101 December 2011 Quality Assurance Topical Report (Qatr), Revision 6 ML1034205492010-10-18018 October 2010 Ouality Assurance Topical Report, Revision 5 CNRO-2010-00002, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2010-04-29029 April 2010 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G RA-10-001, Submittal of Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, Revision 842010-02-0505 February 2010 Submittal of Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, Revision 84 ML0914202742009-05-14014 May 2009 Renewal of Quality Assurance Program Approval for Radioactive Material Packages No. 0019 ML0912605552009-04-28028 April 2009 Renewal of 10 CFR Part 71 Quality Assurance Program Approval Material Packages for Radioactive CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009 Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G ML1101100312008-12-16016 December 2008 Quality Assurance Topical Report, Revision 2 ML0817603042008-06-16016 June 2008 Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 81 ENOC-08-00024, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(e) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2008-04-23023 April 2008 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(e) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML0904103222008-04-15015 April 2008 Entergy'S Quality Assurance Program Manual, Revision 18; Effective: April 15, 2008 RA-08-006, Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 802008-02-0606 February 2008 Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 80 ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16 ML0635304502006-12-14014 December 2006 R. E. Ginna, Change to Common Quality Assurance Program ML0610404932006-04-10010 April 2006 Quality Assurance Topical Report (QATR) NO-AA-10 Revision 77 ML0536102072005-12-0909 December 2005 Annual Submittal of Quality Assurance Program Changes ML0534700942005-12-0505 December 2005 Request for Approval of a Common Quality Assurance Program for Constellation Generation Group, LLC ML0525603262005-09-0707 September 2005 Quality Assurance Topical Report, NO-AA-10, Revision 76 CNRO-2005-00024, Entergy Quality Assurance Program Manual, Revision 122005-04-0606 April 2005 Entergy Quality Assurance Program Manual, Revision 12 ML0509400252005-03-30030 March 2005 Request for Approval of a Common Quality Assurance Program for Constellation Generation Group, LLC ML0506600352005-02-28028 February 2005 Quality Assurance Topical Report (QATR) NO-AA-10 Revision 75 ML0436503322004-12-22022 December 2004 R. E. Ginna, Annual Submittal of Quality Assurance Program Changes ML0427205632004-09-23023 September 2004 Units, 1 & 2, Quality Assurance Policy - Revisions 56, 57, and 58 ML0335704642003-12-17017 December 2003 R. E. Ginna, Annual Submittal of Quality Assurance Program Changes ML0323905282003-08-20020 August 2003 Proposed Revision to Quality Assurance Policy Involving & Reduction in Commitment ML0312600022003-04-24024 April 2003 Issuance of Entergy Quality Assurance Program Manual (Qapm), Revision 8 CNRO-2003-00013, Entergy Quality Assurance Program Manual, Revision 82003-04-24024 April 2003 Entergy Quality Assurance Program Manual, Revision 8 2023-01-31
[Table view] Category:Topical Report
MONTHYEARML23181A1532023-02-28028 February 2023 Attachment 3 - LAS-FLU-001-R-005, Revision 1, LaSalle County Generating Station Unit 1 Reactor Pressure Vessel Fluence Evaluation - End of Cycle 18 ML23181A1542023-02-28028 February 2023 Attachment 4 - LAS-FLU-001-R-002, Revision 1, LaSalle County Generating Station Unit 2 Reactor Pressure Vessel Fluence Evaluation - End of Cycle 18 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 ML22332A4562021-10-12012 October 2021 Attachment 8 - LaSalle County Generating Station Unit 1 Fluence Methodology Report, LAS-FLU-001-R010, Rev. 0 (Non-Proprietary Version) ML22332A4572021-08-12012 August 2021 Attachment 9 - LaSalle County Generating Station Unit 2 Fluence Methodology Report, LAS-FLU-001-R008, Rev. 0 (Non-Proprietary Version) RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology2021-02-10010 February 2021 Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML21194A0272020-12-31031 December 2020 Westinghouse, WCAP-18596-NP Revision 0, Braidwood Unit 1 Reactor Vessel Closure Head Dome-to-Ring Weld ASME Section XI Evaluation of As-Found Indications JAFP-20-0030, Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads2020-04-0606 April 2020 Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads ML20066F6362020-03-0606 March 2020 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline JAFP-20-0006, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102020-02-10010 February 2020 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-19-075, Request for Approval of Change to Quality Assurance Topical Report2019-12-0505 December 2019 Request for Approval of Change to Quality Assurance Topical Report JAFP-19-0016, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102019-02-0808 February 2019 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018 Summary of Changes to Quality Assurance Topical Report, NO-AA-10 ML16271A4512016-05-31031 May 2016 WCAP-18092-NP, Revision 1, Analysis of Capsule V from the Exelon Generation Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program. ML16271A4522016-05-31031 May 2016 WCAP-18107-NP, Revision 0, Analysis of Capsule V from the Exelon Generation Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program. RA-16-007, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, Revision 88, 89 and 902016-02-0808 February 2016 Summary of Changes to Quality Assurance Topical Report, NO-AA-10, Revision 88, 89 and 90 RS-16-018, Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel2016-01-28028 January 2016 Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel ML16228A0422015-12-31031 December 2015 WCAP-18054-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 1 Reactor Vessel Radiation Surveillance Program. BYRON 2016-0078, WCAP-18056-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 2 Reactor Vessel Radiation Surveillance Program.2015-12-31031 December 2015 WCAP-18056-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 2 Reactor Vessel Radiation Surveillance Program. ML15323A2572015-11-19019 November 2015 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change ML15251A3852015-08-31031 August 2015 Attachment 10 - ANP-3324NP, Revision 1, Atrium 10XM Fuel Rod Thermal-Mechanical Design for Quad Cities Unit 2 Cycle 24 Representative Fuel Cycle Design - Licensing Report. (Non-Proprietary) ML15251A3832015-08-31031 August 2015 Attachment 8 - ANP-3338NP, Revision 1, Applicability of Areva BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate. (Non-Proprietary) ML15251A4062015-08-31031 August 2015 Attachment 13 - ANP-3294NP, Revision 1, Nuclear Fuel Design Report Quad Cities Unit 2 Cycle 24 Representative Cycle Atrium 10XM Fuel. (Non-Proprietary) ML15251A3872015-08-31031 August 2015 Attachment 12 - ANP-3328NP, Revision 1, Quad Cities Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel. (Non-Proprietary) ML15251A3862015-08-31031 August 2015 Attachment 11 - ANP-3293NP, Revision 1, Applicability of Areva BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate. (Non-Proprietary) ML14353A2672014-12-15015 December 2014 Summary of Changes to the Constellation Energy Nuclear Group LLC Quality Assurance Topical Report ML13326B0222013-11-21021 November 2013 Constellation Energy Nuclear Group, LLC - Change to Quality Assurance Topical Report, Revision 7 ML13309A6572013-10-25025 October 2013 Constellation Energy Quality Assurance Topical Report, Rev. 7, List of Effective Pages ML13309A6582013-10-0707 October 2013 Constellation Energy Quality Assurance Topical Report, Rev. 7 ML12115A2282012-04-30030 April 2012 Enclosure 5 to Mfn 12-032 - NEDO-33173, Supplement 2, Part 2-A, Revision 1, Applicability of GE Methods to Expanded Operating Domains - Pin-by-Pin Gamma Scan at FitzPatrick, October 2006 RA-12-006, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-102012-02-0606 February 2012 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10 ML12011A0872011-12-16016 December 2011 ISFSI & Nine Mile Point, and R. E. Ginna, ISFSI - Quality Assurance Topical Report, Revision 6 ML12011A1242011-12-0101 December 2011 Quality Assurance Topical Report (Qatr), Revision 6 ML1107600892011-02-28028 February 2011 WCAP-17349-NP, Revision 1, Bypass Test Instrumentation for Byron and Braidwood, Units 1 and 2, Attachment 8 to RS-11-019 ML1034205492010-10-18018 October 2010 Ouality Assurance Topical Report, Revision 5 ML1008504032010-03-31031 March 2010 NEDO-33484, Rev. 0, Safety Analysis Report for Limerick Generating Station Units 1 & 2 Thermal Power Optimization RA-10-001, Submittal of Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, Revision 842010-02-0505 February 2010 Submittal of Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, Revision 84 ML0917705462009-05-31031 May 2009 WCAP-17072-NP, Revision 0, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5), Attachment 9 ML0914202742009-05-14014 May 2009 Renewal of Quality Assurance Program Approval for Radioactive Material Packages No. 0019 ML0904005182009-01-31031 January 2009 ANP-2796(NP), Rev. 0, Zircaloy-BWR Lead Use Channel Program at LaSalle County Generating Station RA-08-076, Request Approval of Change to Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Quality Assurance Topical Report2008-07-31031 July 2008 Request Approval of Change to Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Quality Assurance Topical Report ML0817603042008-06-16016 June 2008 Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 81 RA-08-006, Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 802008-02-0606 February 2008 Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 80 RS-06-088, Requested Information Concerning Pressurizer Heater Sleeve Flaw at Braidwood Station2006-07-17017 July 2006 Requested Information Concerning Pressurizer Heater Sleeve Flaw at Braidwood Station ML0613701022006-05-0101 May 2006 GE-NE-0000-0053-8553-RONP, LaSalle Units 1 and 2 Rod Control Management System Failure Modes and Effects Analysis. RS-06-061, Request for Approval of Change to Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Quality Assurance Topical Report2006-04-24024 April 2006 Request for Approval of Change to Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Quality Assurance Topical Report ML0615300522006-03-31031 March 2006 GE Report GENE-0000-0038-6481-01-R1-NP, Exelon Steam Dryer Dynamic Time History Analyses: Dresden Unit 2 2004 Repair and Dresden Unit 3 2003 and 2004 Repair Dryer Configurations Using Loads from Plant Measurements. RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures For..2005-10-0303 October 2005 License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures For.. ML0525603262005-09-0707 September 2005 Quality Assurance Topical Report, NO-AA-10, Revision 76 2023-02-28
[Table view] |
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4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-19-075 10 CFR 50.54(a)(4)
December 5, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457. and 72-73 Byron Station , Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454. STN 50-455. and 72-68 Calvert Cl iffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. STN 50-317. STN 50-318. and 72-8 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 and 72-1046 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010. 50-237. 50-249. and 72-37 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 and 72-12 RE. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 and 72-67 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373. 50-374 . and 72-70 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352. 50-353. and 72-65 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facil ity Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220. 50-410. and 72-1036
December 5, 2019 U.S . Nuclear Regulatory Commission Page 2 Peach Bottom Atomic Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-12 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171. 50-277. 50-278. and 72-29 Quad Cities Nuclear Power Station , Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254. 50-265. and 72-53
Subject:
Request for Approval of Change to Exelon Generation Company, LLC, Quality Assurance Topical Report In accordance with 10 CFR 50 .54(a)(4), Exelon Generation Company, LLC (EGC), requests approval of a proposed change to the Quality Assurance Topical Report (QATR). The proposed change is a reduction in commitment, and in accordance with 10 CFR 50.54(a)(4), NRC approval is required prior to implementation. The proposed change modifies the internal audit frequency from 24 months to 36 months. The increased period between audits will be supplemented by an interim analysis of functional area performance. The change is applicable to audits implemented to meet the requirements of 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," non-safety programs, and programs that do not have a defined audit frequency, as described in the EGC Quality Assurance Program (QAP). The change does not impact audits performed to meet specific regulations (e.g., Physical Security or Emergency Preparedness). These audits will continue to be performed in accordance with the applicable requirements.
EGC participated in a pre-submittal meeting with the NRC on November 20 , 2019. During this meeting the proposed changes were discussed with the NRC. to this letter describes the proposed QATR change in more detail, the reason for the change, and the basis for concluding that the revised QATR continues to satisfy the criteria of 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." Attachment 2 provides the markup of the affected QATR pages.
EGC requests approval of the proposed changes by December 7, 2020. Once approved, the changes shall be implemented within 90 days.
December 5, 2019 U.S. Nuclear Regulatory Commission Page 3 Should you have any questions concerning this request, please contact Mrs. Linda M. Palutsis at (630) 657-2821.
ReRt:l.P Patrick R. Simpson Sr. Manager Licensing Attachments :
- 1. Evaluation of Proposed Changes
- 2. Markup of Proposed Change to the Exelon Quality Assurance Topical Report cc: NRC Regional Administrator, Region I NRC Regional Administrator, Region Ill NRC Senior Resident Inspector- Braidwood Station NRC Senior Resident Inspector- Byron Station NRC Senior Resident Inspector- Calvert Cliffs Nuclear Power Plant NRC Senior Resident Inspector- Clinton Power Station NRC Senior Resident Inspector- Dresden Nuclear Power Station NRC Senior Resident Inspector- James A. FitzPatrick Nuclear Power Plant NRC Senior Resident Inspector- R.E. Ginna Nuclear Power Plant NRC Senior Resident Inspector- LaSalle County Station NRC Senior Resident Inspector- Limerick Generating Station NRC Senior Resident Inspector- Nine Mile Point Nuclear Station NRC Senior Resident Inspector- Peach Bottom Atomic Power Station NRC Senior Resident Inspector- Quad Cities Nuclear Power Station
ATTACHMENT 1 Evaluation of Proposed Changes Introduction The Exelon Generation Company, LLC (EGC) Quality Assurance Topical Report (QATR) ensures conformance to 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." In accordance with 10 CFR 50.54(a)(4), EGC requests approval of a proposed change to the QATR. The proposed change modifies the internal audit frequency from 24 months to 36 months. The increase period between audits will be supplemented by an interim analysis of functional area performance. The change is applicable to audits implemented to meet the requirements of 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power plants and Fuel Reprocessing Plants," non-safety programs, and programs that do not have a defined audit frequency, as described in the EGC Quality Assurance Program (QAP). The proposed change is a reduction in commitment and, therefore, NRC approval is required prior to implementation.
Background
The EGC QAP complies with administrative controls and quality assurance requirements for performance of internal audits established by the American National Standard Institute (ANSI) and the American Nuclear Society (ANS) standards. The EGC QATR reflects commitment to the applicable ANSI/ANS standards and requires that internal audits be performed every 24 months.
Pre-Submittal Meeting EGC participated in a pre-submittal meeting with the NRC on November 20, 2019. During this meeting the proposed changes were discussed with the NRC. During the meeting EGC clarified that change in the audit frequency for decommissioned units would apply only to Peach Bottom Atomic Power Station, Unit 1, and Dresden Nuclear Power Station, Unit 1, since these permanently shutdown reactors are under the same QAP as the co-located operating units.
The proposed changes would not impact the Three Mile Island Nuclear Station, Unit 1, QAP.
The audit interval extension would apply to EGC's independent spent fuel storage installations (ISFSI), including Calvert Cliffs. The ISFSI at Calvert Cliffs has a specific-license, whereas the other EGC sites have generally licensed ISFSls. The Calvert Cliffs ISFSI Final Safety Analysis Report (FSAR) quality assurance chapter references the EGC QAP. Thus, there are no differences between the QAP requirements for the generally licensed ISFSI and the Calvert Cliffs ISFSI .
Proposed Change EGC is requesting NRC approval to change the internal audit frequency from 24 months to 36 months. Currently QATR Chapter 18, "Audits," requires the following: " ... internal audit program is conducted on a performance driven frequency that is commensurate with the status and importance of the activity to be completed but does not exceed 24 months. Internal audit frequencies required by regulation that are different than the 24-month period are indicated within Appendix B." This proposed change replaces the 24-month frequency requirement with a Page 1
ATTACHMENT 1 Evaluation of Proposed Changes 36-month frequency requirement. The 25% grace period is maintained ensuring that the period between audit performance will not exceed 45 months.
Chapter 18 is also revised to require an evaluation once per calendar year to determine the need for additional audit activities. Results of the evaluation will be assessed and, when necessary, a review of the identified areas of performance weakness will be planned at the earliest possible opportunity.
The proposed change in internal audit frequency is a deviation from EGC QATR commitments to ANSI and ANS standards (References 1, 2, and 3), which state that audits of selected aspects of plant operation shall be performed with a frequency commensurate with their safety significance and in such a manner as to assure that an audit of safety-related activities are completed within a period of 24 months. It also deviates from Regulatory Guide 1.189, "Fire Protection for Nuclear Power Plants," which provides guidance for performance of annual ,
biennial, and triennial audits (Reference 4 ). This is a reduction in commitment pursuant to 10 CFR 50.54(a)(4).
The specific audit topics proposed for the frequency change are:
- Engineering Design Control
- Procurement I Materials Management
- Quality Assurance Functions
- Decommissioned units (applicable to permanently shutdown units not under the control of an NRC approved decommissioning plan)
- Radiological Environmental monitoring Program
- Non-radiological Environmental Monitoring
- Spent Fuel Storage Installations Plant Operation Review Committee Technical specifications and other license conditions In addition, some administrative changes are being included in the markup of Chapter 18 for clarity (Attachment 2). These changes are administrative in nature since the vendor audit frequency will not change, but the wording will be revised to align with the OAP change being proposed. These administrative changes have been evaluated and were determined to not require prior NRC approval per 10 CFR 50.54 , since they do not reduce the commitments in the program description as accepted by the NRC.
Page 2
ATTACHMENT 1 Evaluation of Proposed Changes Justification for Change The proposed change does not represent a reduction in effectiveness or compliance with 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants." A comprehensive system of planned and periodic audits will continue to be performed by independent trained personnel using written procedures to verify compliance with all aspects of the OAP. The internal audit program will continue to be conducted on a performance driven frequency that is commensurate with the status and importance of the activity to be completed .
Performance of functional area and vendor audits will continue to determine effectiveness of the program.
The proposed frequency change supplemented by evaluation is similar to audit requirements outlined in ASME NQA-1-2015, "Quality Assurance for Nuclear Facility Applications," that was endorsed by Regulatory Guide 1.28, "Quality Assurance Program Criteria (Design and Construction)," Revision 5. This revision of NQA-1, Requirement 18, "Audits," Section 201 .2, "Nuclear Facilities After Placing the Facility into Operation," references extending the 2-year internal audit interval to 3 years, not to exceed 4 years with performance of an annual evaluation .
Also, the proposed changes are similar to ANSI/ANS 3.2-2012, "Managerial, Administrative and Quality Assurance Controls for the Operational Phase of Nuclear Power Plants," that was endorsed by Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation),"
Revision 3. This quality standard also, provides guidance in section 3.18.1.1, "Regularly Scheduled Audits," for extending the 2-year frequency not to exceed 4 years with performance of an annual evaluation. In addition, the proposed 36-month audit frequency is consistent with external audit requirements for audit of suppliers and with NRC triennial inspections.
It should be noted that EGC is not adopting NQA-1-2015 or ANSI/ANS 3.2-2012 as part of this proposed change, but is only citing those standards to show that the proposed frequencies are similar to other NRC endorsed standards. The variations between the proposed changes and NRC endorsed quality standards include setting the audit frequency to 36 months with 25%
grace versus the 2-year frequency with a 1-year extension(s) not to exceed 4 years described in NQA-1-2015 and ANSI/ANS 3.2-2012 standards. The proposed evaluation will focus on identifying areas that require audit activity prior to the next scheduled audit, rather than justifying extension.
Functional area audits and evaluations would be separated into three cycles covering a period of 36 months. Each cycle includes a set of audits and evaluations. Results of the completed audits will be reviewed to determine if additional audit activities are necessary prior to their next scheduled performance. Each functional audit area will receive an additional performance analysis (evaluation) within 2 years of the last performed audit based on internal and external data; functional area changes in responsibility, resources, or management; and consideration of the impacts, as applicable, to determine if additional audit activities are necessary prior to the 36-month scheduled performance. These evaluations will meet the intent of the annual evaluation described in NRC endorsed quality standards by ensuring action by the audit organization upon evaluation of adverse performance trends should they exist prior to the next scheduled audit activity. The resulting action will be based on the problem identified and may include one or more of a variety of audit tools, such as simple observations, follow-up reviews, Page 3
ATTACHMENT 1 Evaluation of Proposed Changes limited scope audits up to a full audit of the functional area.
The change in frequency for Fire Protection Program audits do not reduce the effectiveness of the Fire Protection OAP. Audits will be performed on a 36-month frequency and will continue to be comprehensive, risk and performance-based reviews to determine effective implementation of the site and fleet Fire Protection Program . Audits include, but are not limited to, evaluation of organization, personnel, training, program implementation and equipment. Audits will continue to be conducted by an independent Fire Protection Engineer. The audits will be supplemented with an evaluation of the Fire Protection Program implementation activities between scheduled audits.
In aggregate, these changes will continue to meet the fundamental requirements of an internal audit program as described in quality standards endorsed by the NRC and will continue to provide proper coverage of OAP activities. The changes will allow audits to be scheduled at a frequency commensurate with the status and importance of the activity. Evaluations of performance will be used to effectively focus audit resources in areas indicating gaps in OAP implementation.
This change request is written specifically for the EGC OAP, which is based on NQA-1-1994, "Quality Assurance Program Requirement for Nuclear Facilities" (Reference 5). The details of the proposal were developed with industry input through the Nuclear Quality Leadership (NQML) forum. If approved for Exelon, the industry will be able to implement this alternate approach through changes to their OAP under 10 CFR 50 .54(a), regardless of the specific version of quality standards that form the basis of their OAP. EGC requests that NRC approval documentation acknowledges this approach for industry reference.
Precedent None.
References
- 1. ANSI N18.7-1972, "Administrative Controls for Nuclear Power Plants (Peach Bottom)"
- 2. ANSI N18.7-1976/ANS 3.2, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants (Limerick, Fitzpatrick, Clinton)"
- 3. ANSI/ANS 3.2-1988, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants (Braidwood, Byron, Dresden, LaSalle and Quad Cities)"
- 4. Regulatory Guide 1.189, "Fire Protection for Nuclear Power Plants"
- 5. NQA-1-1994, "Quality Assurance Program Requirement for Nuclear Facilities" Page4
ATTACHMENT 2 Markup of Proposed Changes to the Exelon Quality Assurance Topical Report
AUDITS Chapter 18 18.1. SCOPE A documented, comprehensive system consisting of regulatory audits of the Company and its vendors are conducted to verify OAP compliance, adequacy, and effectiveness. Audits are conducted in accordance with written procedures or checklists. Audits are performed to the requirements of ASME NQA-1 to evaluate the audited organization and to assure completion of required corrective actions, commitments, or improvements and determine effectiveness in meeting program objectives.
18.2. REQUIREMENTS 18.2.1. General 18.2.1.1 Scheduling The internal audit program is conducted on a performance driven frequency that is commensurate i.vith the status and importance of the activity to be completed but does not exceed 24 months. Internal audit frequencies required by regulation that are different than the 24 month period are indicated within Appendix B, Audit Frequency. Audit frequencies are determined based on a consideration of the risk and consequences with respect to the activities audited The internal audit program is conducted on a performance driven frequency that is commensurate with the status and importance of the activity to be completed . Audits governed by regulations will be performed on a frequency specified by the regulation. All other audits are nominally scheduled at a 36-month frequency. Audits shall be performed at the intervals designated in Appendix B, Audit Frequency. Schedules are based on the month in which the audit starts.
An evaluation will be performed once per calendar year, to determine the need for additional audit activities. When determined necessary, an additional audit activity will be performed within a timeframe established by the evaluation .
Audits or surveys of vendors and their sub-tier suppliers are performed to a pre-established schedule. Audits are nominally scheduled at a 36-month frequency. Documented supplier performance monitoring is performed in accordance with approved procedures as an acceptable alternate to the performance of the annual evaluation of suppliers. The management position responsible for audits and programs or designee, shall review and approve the audit I survey schedule and checklists, and sign reports . Schedules are Page 1 of 5 Revision 9495
AUDITS Chapter 18 reviewed semi-annually and revised accordingly to assure that suppliers are audited or surveyed as required .
Audits may be extended beyond their originally scheduled due date based on the following criteria:
&_Audits shall be performed at the intervals designated in Appendix B, Audit Frequency. Schedules are based on the month in i.vhich the audit starts.
~ For internal and vendor audits or surveys. a maximum extension not to exceed 25 percent of the audit interval is allowed . Unless extension is allowed by regulations. regulatory required audits will be performed on a frequency not to exceed 24 months.
IGB. For supplier audits and evaluation, a maximum extension not to exceed 25 P-ercent of the audit interval is allo vved . That is to say that, for 1
Admin istrative audits on a 24 month freg:Yfillfil', the maximum time between s ~ ific changes included audits does not exceed 30 months. Likewise, audits on an annual (12 for clarity. See month) freguency do not extend beyond 15 months. Audits of Emergency page 2 for discussion. Preparedness, Cyber Security, and Security are not subject to the extension and will be performed on a frequency not to exceed 12 months (or not to exceed 24 months if performed on a 24 month frequency) .
D. When an audit interval extension greater than one month is used, the next audit for that particular audit area is scheduled from the original anniversary month rather than from the month of the extended audit.
Items B aP-plies to SUP-Plier audits and evaluations except that a total combined interval for any three consecutive insP.ection or audit intervals does not exceed 3.25 times the specified inspection or audit interval.
18.2.1.2. Preparation A documented plan or an agenda identifies the audit scope, requirements, personnel, activities to be evaluated, organizations to be notified, applicable documents, and schedule . An approved checklist or procedure for each scheduled audit identifies the requirements of the area or items to be evaluated. Audit plans, agendas, checklists, and procedures as applicable are prepared in advance under the direction of an Audit Team Leader.
18.2.1.3. Personnel Experienced and qualified personnel perform audits and are familiar with written procedures, standards, and processes applicable to the area being Page 2 of 5 Revision 9495
AUDITS Chapter 18 evaluated. Audit personnel shall have sufficient authority and organizational freedom to make the audit process meaningful and effective and shall not have direct responsibilities in the areas to be audited . They shall have access to the plant records necessary to fulfill their function.
The Audit Team Leader shall organize and direct audits and ensure the team collectively has the required experience or training for the activities to be evaluated. Technical Specialists may supplement the team to provide additional experience and competence.
18.2.1.4. Performance Audits are initiated early to assure effective quality assurance during design, procurement, manufacturing, construction, installation, inspection, testing, and operations. Additional unscheduled audits may also be performed at various stages of activities, based on the nature and safety significance of the work being done; to verify continued adherence to and effectiveness of the quality systems. Objective evidence shall be examined to the extent necessary to determine that a quality program is being effectively implemented.
18.2.1.5. Reporting and Follow-up An audit report includes the description of the audit scope, identification of the team and personnel contacted during audit activities, a summary of results (including a statement on effectiveness of the OAP elements), and a description of each finding . The ATL shall sign the audit report for which he or she is responsible .
Audit results are documented and distributed to the management position responsible for NOS, and to the appropriate managerial level of the organization having responsibility for the area or activity audited. Findings or deficiencies requiring prompt corrective action are reported immediately to the management of the audited organization.
Findings , deficiencies, and recommendations of each audit shall be reported to appropriate site management and the management position responsible for NOS. All findings of noncompliance with NRC requirements, and any significant nuclear safety or quality issues requiring escalated action, will be directed through the management position responsible for NOS to the President and CNO in accordance with procedural requirements.
Page 3 of 5 Revision 9495
AUDITS Chapter 18 Responsible management shall take the necessary actions to correct findings identified in the audit. They will identify the corrective action to be taken, actions that will prevent recurrence as applicable, and a schedule for implementing these actions. Responses to audit findings are reviewed for adequacy.
Follow-up verification of the completion of scheduled corrective action commitments are performed by NOS to assure findings or adverse conditions are corrected in accordance with procedural requirements . Follow-up action of previous deficient areas or adverse conditions (including re-audit) is taken to verify that corrective action has been completed, is effective, implementation continues, and is properly documented, when indicated .
18.2.1.6. Records Audit_results are documented... and reports are generated and retained as applicable. Associated documentation is on file at the appropriate location.
Personnel qualification records for audit team members are established, maintained, and reviewed as required .
18.2.2. Vendor Audits Audits or surveys of vendors and their sub tier suppliers are performed to a pre established schedule. Audits are performed on a triennial basis.
Documented supplier performance monitoring is performed in accordance
\Nith approved procedures as an acceptable alternate to the performance of the annual evaluation of suppliers. The management position responsible for audits and programs or designee, shall reviei,,v and approve the audit/survey schedule and checklists, and sign reports . Schedules are reviewed semi annually and revised accordingly to assure that suppliers are audited, or surveyed as required.
Audit program requirements are imposed on suppliers by appropriate contract or procurement documents. The Company's active participation in nuclear industry audits provides an alternative means to fulfilling its responsibility for examining supplier activities .
18.2.3. Independent Management Audit A periodic audit (not to exceed 24 months) of the status and adequacy of the OAP is performed by an independent organization to assure that audits are being accomplished to program requirements . In addition, this will include an evaluation of the independent review as defined in Chapter 2, section 2.2.6.
The management position responsible for NOS submits the results of this Page 4 of 5 Revision 9495
AUDITS Chapter 18 audit to the President and CNO. The periodic audit will include a sampling of sites and are nominally scheduled at a 36-month frequency with a 25 percent grace allowed. A self-assessment will be performed once per calendar year to evaluate the need for additional audit activities.
Page 5 of 5 Revision 9495
Audit Frequency APPENDIX B Internal audits shall be conducted on a performance driven frequency, not to exceed 24 months or at the frequencies in calendar months as indicated below, in accordance with the Company's OAP. Audits shall include the following safety-related functions as applicable:
AUDIT FREQUENCY
- a. The conformance of unit operation to provisions contained 24-36 Months within the technical specifications and applicable license conditions.
- b. The adherence to procedures, training, and qualification of the 24-36 Months station staff.
- c. The results of actions taken to correct deficiencies occurring in 24-36 Months facility equipment, structures , systems, components, or method of operation that affect nuclear safety (CAP) .
- d. The performance of activities required by the Quality Assurance 24-36 Months Program to meet the criteria of Appendix B of 10 CFR 50.
- Engineering - Design Control ,
- Procurement I Materials Management
- Quality Assurance Functions (internal and vendor audit\
assessment activities are evaluated by NIEP.)
- e. The fire protection programmatic controls including the 24-36 Months implementing procedures (by qualified Nuclear Oversight personnel).
- f. The fire protection equipment and program implementation, 24-36 Months including loss prevention, utilizing either a qualified offsite licensee fire protection engineer or an outside, independent fire protection consultant. An outside, independent fire protection consultant shall be used.:. at least every second year.
- g. The Radiological Environmental Monitoring Program (REMP) 24-36 Months and its results .
- h. The Offsite Dose Calculation Manual (ODCM) and 24-36 Months implementing procedures.
Page 1 of 3 Revision 9495
Audit Frequency APPENDIX B AUDIT FREQUENCY
- i. The Process Control Program (PCP) and implementing 24--36 Months procedures for the solidification of radioactive wastes.
- j. The non-radiological environmental monitoring activities 24--36 Months required by the Appendix B of the Facility Operating Licenses.
(Note: Dresden, Ginna, and TMI do not have an Environmental Appendix to their Facility Operating Licenses .)
- k. Randomly selected procedures to ensure that the programmatic 24--36 Months control processes used to assure that procedures are technically and administratively correct prior to use are resulting in timely and accurate procedure revisions .
I. The Security Plan and implementing procedures per 10 CFR 24 Months 73 .55. Minimally review each element of the physical protection program at least every 24 months. Including :
(i) Within 12 months following initial implementation of the physical protection program or a change to personnel, procedures, equipment, or facilities that potentially could adversely affect security.
(ii) As necessary based upon site-specific analyses ,
assessments, or other performance indicators.
(Reference 10 CFR 73 .55 and 10 CFR 50 .54(p)(3)(ii))
- m. The Emergency Plan and implementing procedures (Reference 4-&24 Months 10 CFR 50 .54(t)(1 )(ii) for lesser frequency requirements) .
- n. Deleted
- 0. The conformance of Spent Fuel Storage Installation operation to 24--36 Months provisions contained within the technical specifications and applicable license conditions and results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, components , or methods of operation affecting nuclear safety (Reference NU REG I CR-6407, and 10 CFR 72, Subpart G) (ISFSI sites only) .
- p. Access Authorization Program (1 OCFR73 .56) 24 Months (Initial Audit frequency is 12 months and 24 months thereafter)
(Ref. RIS 2005-14)
Page 2 of 3 Revision 9495
Audit Frequency APPENDIX B AUDIT FREQUENCY
- q. Personnel Access Data System (PADS) (10 CFR 73.56) 24 Months (Initial Audit frequency is 12 months and 24 months thereafter)
(Ref RIS 2005-14)
- r. Deleted
- s. Fitness For Duty (FFD) Program (10 CFR 26.41) 24 Months
- t. Station Black Out (Reg . Guide 1.155, Appendix A) 24-36 Months Audits should be conducted and documented to verify compliance with design and procurement documents, instructions, procedures, drawings, and inspection and test activities developed to comply with 10 CFR 50 .63. (Calvert Cliffs, Dresden, FitzPatrick, LaSalle, Limerick, Nine Mile Point Units 1 and 2, Oyster Creek, Quad Cities, and Three Mile Island Only)
- u. Radiation Protection activities as defined in 10 CFR 20 . 24-36 Months
- v. Plant Operations Review Committee (PORC) 24-36 Months
- w. Decommissioned Units 24-36 Months
- x. Cyber Security Program (10 CFR 73.55(m)). 24 Months (Initial Audit frequency is 12 months and 24 months thereafter)
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