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MONTHYEARULNRC-06282, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-23023 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ULNRC-06311, Final Notification of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-07-0606 July 2016 Final Notification of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ULNRC-06310, Final Notification of Full Compliance with March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis (Order No. EA-12-049)2016-07-0606 July 2016 Final Notification of Full Compliance with March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis (Order No. EA-12-049) Project stage: Other ULNRC-06330, Final Safety Analysis Report Revision OL-22 and Technical Specification Bases Revision 132016-11-10010 November 2016 Final Safety Analysis Report Revision OL-22 and Technical Specification Bases Revision 13 Project stage: Request ML17010A3322017-02-0202 February 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Approval 2016-02-23
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Category:Final Safety Analysis Report (FSAR)
MONTHYEARML23318A1082023-12-28028 December 2023 FSAR Chapter 1, Figures Redacted ML23165A2432023-06-14014 June 2023 FSAR Markup for FSAR Site Addendum (SA) Sections 13.1.3.1, 13.1.3.1.18, and 13.1.3.1.19 ML23062A6432022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 15, Figure 15.6-2, Revision 17, Pressurizer Pressure and Vessel Average Temperature Transients for Inadvertent Opening of a Pressurizer Safety Valve ML23062A6492022-12-29029 December 2022 Submittal of Revision OL-26 to Final Safety Analysis Report and Revision 18 to Technical Specification Bases ML23062A6542022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 18, Figures ML23062A6532022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 17, Quality Assurance ML23062A6522022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 16, Figures ML23062A6512022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 16, Technical Requirements ML23062A6502022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 18, Clarification of TMI Action Plan Requirements ML23062A6472022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 6, Figures ML23062A6452022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML23062A6442022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML23062A6422022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML23062A6412022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 12, Radiation Protection ML23062A6402022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant ML23062A6392022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 8, Figures ML23062A6382022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Figures ML23062A6372022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Change Notice Log ML23062A6362022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 13, Conduct of Operations ML23062A6352022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 15, Accident Analysis ML23062A6342022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 10, Figures ML23062A6332022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML23062A6322022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 12, Figures ML23062A6312022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 4, Reactor ML23062A6302022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 2, Site Characteristics ML23062A6292022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 9, Figures ML23062A6062022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 8, Electric Power ML23062A6072022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 5, Figure 5.2-2, Primary Coolant Leak Detection Response Time ML23062A6082022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, List of Effective Figures ML23062A6092022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML23062A6112022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, List of Effective Sections ML23062A6122022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 15, Figures ML23062A6132022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, List of Effective Tables ML23062A6152022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 2, Figures ML23062A6162022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 15, Figure 15.6-1, Revision 17, Nuclear Power and DNBR Transients for Inadvertent Opening of a Pressurizer Safety Valve ML23062A6172022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 14, Initial Test Program ML23062A6252022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 5, Figures ML23062A6282022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 3, Figures ML23062A6182022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML23062A6272022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 7, Figures ML23062A6262022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 11, Figures ML23062A6202022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 4, Figures ML23062A6212022-12-29029 December 2022 Revision OL-26 to Final Safety Analysis Report, Chapter 18, Figure 18.2-12, Functional Diagram Reactor Core Subcooling Monitor 2023-06-14
[Table view] Category:Letter type:ULNRC
MONTHYEARULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection 2024-06-26
[Table view] Category:Technical Specification
MONTHYEARULNRC-06880, Proposed Technical Specification Bases Changes (Mark-up)2024-06-0606 June 2024 Proposed Technical Specification Bases Changes (Mark-up) ML24158A5232024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition ML24158A5252024-06-0606 June 2024 Revised Technical Specification Pages (Clean Pages) ML24158A5242024-06-0606 June 2024 Proposed Technical Specification Changes (Mark-up) ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ML23310A0512023-11-0606 November 2023 EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document ML23227A1282023-08-15015 August 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23227A1272023-08-15015 August 2023 Corrected Proposed Technical Specification 55.16 Changes (Markup) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1232023-03-29029 March 2023 Attachment 3: Marked-Up Technical Specification, Bases Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML23088A2542023-03-23023 March 2023 EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document ML23052A0472023-02-21021 February 2023 Enclosure 5 - Revised Technical Specification Bases (for Information Only) ML23067A1822022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems ML23067A1752022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation ML23067A1742022-12-29029 December 2022 Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems ML23067A1842022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System ML23067A1792022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Implemented Change Notice Log ML23067A1762022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs) ML23067A1862022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits ML23067A1772022-12-29029 December 2022 Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls) ML23067A1782022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems ML23067A1852022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations ML23067A1832022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Table of Contents ML23067A1812022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls) ML23067A1802022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections2022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, List of Effective Sections ML22335A5112022-12-0101 December 2022 Attachment 2 - Proposed TS Bases Changes (Markups) ML22335A5092022-12-0101 December 2022 Description and Assessment of the Proposed Change ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22216A2422022-08-0404 August 2022 Proposed Technical Specification Changes (Mark-Up) ML22181B1342022-06-30030 June 2022 Attachment 4 - Replacement for Attachment 4, Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information), of ULNRC-06688 ML22153A1792022-06-0202 June 2022 Attachment 3 - Marked-Up Technical Specifications Bases ULNRC-06686, Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up)2021-12-0909 December 2021 Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up) ML21335A4572021-12-0101 December 2021 Enclosure 5: Proposed Technical Specification Bases Changes (Mark-up - for Info Only) ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4122021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes 2024-06-06
[Table view] Category:Bases Change
MONTHYEARML24158A5252024-06-0606 June 2024 Revised Technical Specification Pages (Clean Pages) ULNRC-06880, Proposed Technical Specification Bases Changes (Mark-up)2024-06-0606 June 2024 Proposed Technical Specification Bases Changes (Mark-up) ML24158A5232024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition ML24158A5242024-06-0606 June 2024 Proposed Technical Specification Changes (Mark-up) ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ML23310A0512023-11-0606 November 2023 EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document ML23227A1282023-08-15015 August 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23227A1272023-08-15015 August 2023 Corrected Proposed Technical Specification 55.16 Changes (Markup) ML23088A1232023-03-29029 March 2023 Attachment 3: Marked-Up Technical Specification, Bases Pages ML23088A2542023-03-23023 March 2023 EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document ML23052A0472023-02-21021 February 2023 Enclosure 5 - Revised Technical Specification Bases (for Information Only) ML23067A1822022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems ML23067A1802022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems ML23067A1812022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls) ML23067A1742022-12-29029 December 2022 Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems ML23067A1762022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs) ML23067A1752022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation ML23067A1782022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems ML23067A1772022-12-29029 December 2022 Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls) ML23067A1792022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Implemented Change Notice Log ML23067A1832022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Table of Contents ML23067A1842022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System ML23067A1852022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations ML23067A1862022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections2022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, List of Effective Sections ML22335A5092022-12-0101 December 2022 Description and Assessment of the Proposed Change ML22335A5112022-12-0101 December 2022 Attachment 2 - Proposed TS Bases Changes (Markups) ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ML22216A2422022-08-0404 August 2022 Proposed Technical Specification Changes (Mark-Up) ML22181B1342022-06-30030 June 2022 Attachment 4 - Replacement for Attachment 4, Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information), of ULNRC-06688 ML22153A1792022-06-0202 June 2022 Attachment 3 - Marked-Up Technical Specifications Bases ULNRC-06686, Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up)2021-12-0909 December 2021 Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up) ML21335A4572021-12-0101 December 2021 Enclosure 5: Proposed Technical Specification Bases Changes (Mark-up - for Info Only) ML21294A3982021-10-21021 October 2021 Attachment 4 - Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information) ML21272A1732021-09-28028 September 2021 Enclosure 5 - Proposed TS Bases Changes (for Information Only) ML21272A1722021-09-28028 September 2021 Enclosure 4 - Revised Technical Specification Pages ML21272A1712021-09-28028 September 2021 Enclosure 3 - Proposed Technical Specification Changes (Mark-up) ML21194A2662021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.1, Reactivity Control Systems ML21195A3212021-06-22022 June 2021 Technical Specification Bases Implemented Change Notice Log ML21194A2732021-06-22022 June 2021 Technical Specification Bases, List of Effective Sections ML21194A2722021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.2, Power Distribution Limits ML21194A2712021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.9, Refueling Operations ML21194A2692021-06-22022 June 2021 Technical Specification Bases, Table of Contents ML21194A2702021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.4, Reactor Coolant System ML21194A2682021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.8, Electrical Power Systems ML21194A2612021-06-22022 June 2021 Technical Specification Bases, Chapter B 3.7, Plant Systems ML21194A2622021-06-22022 June 2021 Technical Specification Bases, Chapter 3.3, Instrumentation 2024-06-06
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VIAmeren Callaway Plant MISSOURI November 10, 2016 ULNRC-06330 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC20555-0001 10 CFR 50.7l(e) 10 CFR 54.37(b) 10 CFR 50.4(b)(6)
Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
RENEWED FACILITY OPERATING LICENSE NPF-30 FINAL SAFETY ANALYSIS REPORT REVISION OL-22 ANDTECHNICAL SPECIFICATION BASES REVISION 13 In accordance with the requirements of 10 CFR 50.71(e) and 10 CFR 50.4(b)(6), Union Electric Company (Ameren Missouri) herewith submits the Callaway Plant Final Safety Analysis Report (FSAR) (Standard Plant and Site Addendum) updated through Revision OL-22. The FSAR has been revised to include changes made to the plant up to 6 months prior to the date of this filing.
Additionally, pursuant to Callaway Technical Specification 5.5.14, "Technical Specifications (TS)
Bases Control Program," Ameren Missouri is also submitting Revision 13 to the Callaway Plant
- Technical Specification*Bases (TS Bases) since the TS Bases update is required to be submitted at a frequency consistent with 10 CFR 50.71(e). The TS Bases have been revised to reflect changes made to the plant up to 6 months prior to the date of this filing.
Based on NRC Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents,"
Ameren Missouri has reviewed Revision OL-22 of the FSAR for sensitive information. Consequently, Revision OL-22 of the FSAR is being provided on two CD-ROMs (CDs). One version, ori CD 1 (provided as Enclosure 2), is a complete text of the FSAR and contains sensitive information which should be withheld from public disclosure per the guidance in RIS 2015-17. The information that Ameren Missouri has identified to be withheld is designated by the statement "Withhold per RIS 2015-17" at the top and bottom of the page. The second version, on CD 2 (provided as Enclosure 3),
is a redacted text of the FSAR. Each page on which information was withheld contains the
- PO Box 620 Fulton, MO 65251 . AmerenMissouri.com **************
ULNRC-06330 November 10, 2016 Page2 designation "Withheld per RIS 2015-17." The version on CD 2 is therefore suitable for public disclosure.
The documents on both CDs are being transmitted in electronic format in accordance with the guidance of Regulatory Issue Summary (RIS) 2001-05, dated January 25, 2001.
In addition to the updated FSAR and TS Bases, the enclosed CD-ROMs include the Callaway Plant Operating License, Technical Specifications, and NRC Orders for Callaway Plant updated through November 10, 2016. Also included is an "FSAR Change Log" file that provides information on the FSAR Change Notices that were incorporated into FSAR Revision OL-22.
All of the provided documents are in the PDF Normal format and can be viewed using Adobe Acrobat Reader. A copy of Adobe Acrobat Reader 5.0 with the Search plug-in is included on the CD-ROMs.
Also included is an "eLDL Readme" file that provides a brief description of the format and some basic guidance for using the electronic licensing document library.
This submittal contains PDF files that contain hyperlinks to other files contained on the CD-ROM.
These hyperlinks are not essential to the use of the filing. Any material referenced by a hyperlink to another PDF that was essential for the use of this filing has either been included by reference or submitted as part of this filing. In addition, it should be noted that the document file naming convention was created prior to the NRC requirement to use the ISO 9660 naming convention, and due to the interactive linking within the documents, these documents cannot be readily converted to the ISO 9660 naming convention.
In addition to the documents described above, Enclosure 1 contains a report describing how the effects of aging of newly-identified structures, systems, or components (SSCs) will be managed, as required by 10. CFR 54.37(b).
This letter contains no new commitments. Please contact Tom Elwood, Supervising Engineer, Regulatory Affairs and Licensing, at (314) 225-1905 for any questions you may have regarding this submittal.
I**
ULNRC-06330 November 10, 2016 Page 3 I declare under penalty of perjury that the foregoing is true and correct Sincerely, Executed on: LJ.,,,, IO,. .101(, "'<f' e-:J~
Roger C. Wink AN c, g~ I Manager, Regulatory Affairs TAW/sls Enclosure 1 - Summary of Newly Identified SSCs Within the Scope of the Aging Management Program Enclosure 2 - CD 1 Enclosure 3 - CD 2
l*
ULNRC-06330 November 10, 2016 Page4 cc: Mr. Kriss M. Kennedy Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. L. John Klos Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08H4 Washington, DC 20555-0001 Caitlin Murphy Institute of Nuclear Power Operations 700 Galleria Parkway SE, Suite 100 Atlanta, GA 30339
ULNRC-06330 November 10, 2016 Page 5 Index and send hardcopy to QA File Al60.0761 Hard copy:
Certrec Corporation 6100 Western Place, Suite 1050 Fort Worth, TX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via FSAR ULNRC Distribution:
w/o attachments F. M. Diya T. E. Herrmann S. P. Banker R. C. Wink T. B. Elwood Corporate Communications NSRB Secretary Mr. Greg Voss; REP Manager (SEMA)
STARS Regulatory Affairs Mr. Jay Silberg (Pillsbury Winthrop Shaw Pittman LLP)
Missouri Public Service Commission Ms. Leanne Tippett-Mosby (DNR) to ULNRC-06330 Enclosure 1 to ULNRC-06330 Summary of Newly Identified Structures, Systems, and Components (SSCs) Within the Scope of the Aging Management Program to ULNRC-06330 REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW EFFECTS OF AGING OF NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED This update follows existing regulatory requirements and guidance regarding the appropriate level of detail for reports under 10 CFR 54.37(b), including details presented in "Frequently Asked Questions (FAQs) About License Renewal" of Inspection Procedure (IP) 71003, "Post-Approval Site Inspection for License Renewal." This report provides summary information and technical details as required by 10 CFR 54.37(b) for the period between July 31, 2014 through June 23, 2016.
Regulatory Requirements and Guidance 10 CFR 54.37(b)
After the renewed license is issued, the FSAR update required by 10 CFR
- 50. 71 (e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analyses in accordance with Section 54.21. This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in section 54.4(b) will be effectively maintained during the period of extended operation.
RIS 2007-16, Revision 1 Newly Identified Systems. Structures. and Components The intent of 10 CFR 54.37(b) is to capture those SSCs that, if they had been identified at the time of the license renewal application, would have been subject to an aging management review or evaluation of TLAAs. In the context of 10 CFR 54.37(b), newly identified SSCs that should be included in the next FSAR update required by 10 CFR
- 50. 71 (e) are those SSCs that meet one of the two following conditions:
(1) There is a change to the current licensing basis (CLB) that meets the following criteria:
- The change impacts SSCs that were not in scope for license renewal when the NRG approved the license renewal application.
- The SSCs would have been in the scope of license renewal based on the CLB change if 10 CFR 54.4(a) were applied to the SSCs.
(2) SSCs were installed in the plant at the time of the license renewal review that, in accordance with the CLB at the time, should have been included in the scope of license renewal per 10 CFR 54.4(a) but were not identified as in scope until after issuance of the renewed license.
1 to ULNRC-06330 SSCs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions of 10 CFR 54.37(b).
Identification of SSCs under 10 CFR 54.37(b)
The language of 10 CFR 54.37(b) does not limit how or who finds newly identified SSCs. A licensee may identify SSCs that should be within the scope of its license renewal program at any time. The NRG staff may also discover newly identified SSCs.
One way to identify these SSCs is through the LR-ISG process.
Summary of Newly Identified Systems, Structures, or Components (SSCs)
Alternate Emergency Power System Ameren Missouri installed an Alternate Emergency Power System (AEPS) which provides power to the non-safety auxiliary feedwater pump, which is credited in the NFPA 805 fire protection analysis; therefore, it performs a fire protection function for License Renewal (LR).
The AEPS consists of four skid-mounted diesel generators which include cooling systems, exhaust piping, mufflers and rain caps, fuel lines and fuel tanks, metal sided structures, and concrete foundations. Support equipment includes an electric transformer and switchgear, including metal sided structures, concrete foundations, above and underground power cables, and electrical connections. The following AMPs are credited for managing the aging of the AEPS during the Period of Extended Operation (PEO):
Bolting Integrity (FSAR SP 19.1.8)
External Surfaces Monitoring of Mechanical Components (FSAR SP 19.1.21)
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (FSAR SP 19.1.23)
Fuel Oil Chemistry (FSAR SP 19.1.16)
The following exception is taken for inspection of the AEPS fuel oil storage tanks:
NUREG-1801 Rev 2 Xl.M30, Fuel Oil Chemistry, requires that at least once during the 10-year period prior to the period of extended operation and every 10 years during the period of extended operation, each diesel fuel tank is drained and cleaned, the internal surfaces are visually inspected (if physically possible) and volumetrically-inspected if evidence of degradation is observed during visual inspection, or if visual inspection is not possible. The Callaway AEPS fuel oil storage tanks cannot be physically cleaned and inspected due to design constraints associated with a secondary containment tank that limits access.
The presence of fuel oil in the secondary containment of these fuel oil storage tanks provides a local alarm which would indicate a leak in the primary tank.
Equipment operators monitor the alarm panel as part of daily rounds. The local 2
to ULNRC-06330 alarm provides a method of alerting plant staff to aging effects on the tank prior to the degradation challenging the tank's ability to maintain the intended function of the AEPS during the period of extended operation.
Lubricating Oil Analysis (FSAR SP 19.1.24)
One-Time Inspection (FSAR SP 19.1.18)
Closed Treated Water Systems (FSAR SP 19.1.11)
Selective Leaching (FSAR SP 19.1.19)
Structures Monitoring (FSAR SP 19.1.31)
Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (FSAR SP 19.1.34)
Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (FSAR SP 19.1.36)
Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (FSAR SP 19.1.37)
Table 1 in Attachment 1 to this enclosure identifies the components and structures requiring aging management and provides how the effects of aging are managed so that the intended functions are effectively maintained during the period of extended operation. The use of the aging management programs credited in Table 1 are consistent with NUREG-1801 Rev 2, Generic Aging Lessons Learned (GALL) Report,"
and those approved in the Callaway Safety Evaluation Report, NUREG-2172 with one exception of Fuel Oil Chemistry described above.
Doors Credited as Fire Barriers Two (2) newly identified doors are fire barriers which are credited in the NFPA 805 fire protection analysis. The following AMPs are credited for managing the aging of these doors during the PEO:
Structures Monitoring (FSAR SP 19.1.31)
Fire Protection (FSAR SP 19.1.13)
Table 2 in Attachment 1 of this enclosure identifies how the effects of aging are managed for the subject fire barrier doors so that the intended functions are effectively maintained during the period of extended operation. The use of the aging management programs credited in Table 2 is consistent with NUREG-1801 Rev 2 and is approved in the Callaway Safety Evaluation Report, NUREG-2172.
3 to ULNRC-06330 Newly Identified Time Limited Aging Analyses (TLAA)
Replacement Reactor Vessel Closure Head The Replacement Reactor Vessel Closure Head (RRVCH) project design specification requires that the pressure retaining and integrally attached material shall meet all the requirements for ASME Class 1 vessels. The original Construction Code for Callaway closure head are ASME Section Ill, 1971 Edition, with Addenda through winter 1972 for the RRVCH and the Control Rod Drive Mechanism (CROM) adapter and ASME Section Ill, 1974 Edition with Addenda through winter 1974 for the CROM housings.
The design of ASME Ill Class 1 components requires fatigue analyses. These fatigue analyses are required to demonstrate that the Cumulative Usage Factor (CUF) for the component will not exceed the Code design limit of 1.0 when the component is exposed to all of the postulated transients.
The RRVCH assembly design specification states that the cumulative operating period shall cover 45 calendar years. The fatigue analyses depend on the numbers of anticipated transients over the life of the plant. The numbers of design transients used in the fatigue analyses are consistent with the original design basis listed in FSAR SP Table 3.9(N)-1 SP and monitored by the Fatigue Monitoring program (FSAR SP 19.2.1 ).
The Class 1 fatigue analyses of the RRVCH, CRDMs, and Core Exit Thermal Nozzle Assemblies (CETNA) components used the design basis numbers of events. The RRVCH, CRDMs, and CETNAs were replaced in Refueling Outage 20 (Fall 2014).
These fatigue analyses are based on a 45-year design life, which ends in 2059. This extends beyond the period of extended operation; therefore, these fatigue analyses are new TLAAs. The design is valid through the period of extended operation and the TLAAs are dispositioned in accordance with 10 CFR 54.21(c)(1)(i). FSAR SP Section 19.3.2.1.5 is added to identify the TLAAs associated with the design of the RRVCH, CROM, and CETNA.
In addition to the new TLAAs associated with the design of the RRVCH, CROM, and CETNA, the RRVCH modification removed the TLAA associated CROM canopy weld crack growth from the design basis.
HOPE Break Exception Callaway revised FSAR SP Section 3.6.2.1.2.4 and FSAR SP Table 3.6-2 to add a low stress exclusion criterion for high-density polyethylene (HOPE) piping.
The break exception criterion described in FSAR SP Section 3.6.2.1.2.4 and FSAR SP Table 3.6-2, which requires the sum of Service Level B Longitudinal Stress Equation and Alternate Thermal Expansion or Contraction Evaluation to be less than 0.4 (1.2S +
1100), assumes an allowable stress that is based on 50 years. The replacement of buried Essential Service Water (ESW) piping with HOPE material began in 2008. This 4
Enclosure I to ULNRC-06330 extends the exception beyond the period of extended operation therefore, the TLAA will remain valid for the period of extended operation, and is dispositioned in accordance with 10 CFR 54.21 (c)(1 )(i). FSAR SP Section 19.3.6.11 is added to identify the TLAA associated with the Break Exception for HOPE Piping.
5
Attachment 1 to Enclosure 1 to ULNRC-06330 Attachment 1 The following tables contain the newly identified components and structures requiring aging management and provide how the effects of aging are managed so that the intended functions are effectively maintained during the period of extended operation.
Table 1 Alternate Emergency Power System Aging Management Review
.. '*' *' : A9i!1g*Effect
>/' . 'r,,,
- 'Intended* " * *E~vjforim~nts,.. :;t,
- Cor,nporu~nt Type -~ ' 1 Material', * . ?'
- :Req"uirin'g * *~ging 1V1ana~ementP..rogi"arn .'
F,u*n~tion 111* *
.Internal/External.:" . ' . '
' ,~
. .. . ,* . ' \" . , ,. *,
/ ,' '* *'
Loss of Preload Closure Bolting PB Carbon Steel Plant Indoor Air (Ext) Bolting Integrity (FSAR SP 19.1.8)
Loss of Material External Surfaces Monitoring of Plant Indoor Air (Ext) Loss of Material Mechanical Components Damper PB Carbon Steel (FSAR SP 19.1.21)
Ventilation Inspection of Internal Surfaces in Loss of Material Miscellaneous Piping and Ducting Atmosphere (Int)
Components (FSAR SP 19.1.23)
Fuel Oil Chemistry (FSAR SP 19.1.16)
Filter PB Fuel Oil (Int) Loss of Material Aluminum One-Time Inspection (FSAR SP 19.1.18)
Plant Indoor Air (Ext) None None Fuel Oil Chemistry Fuel Oil (Int) Loss of Material (FSAR SP 19.1.16)
One-Time Inspection Filter PB Carbon Steel (FSAR SP 19.1.18)
External Surfaces Monitoring of Plant Indoor Air (Ext) Loss of Material Mechanical Components (FSAR SP 19.1.21) 6
Attachment 1 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review
- .. ), ' ",~ " ,, *\', ,<<
~rivfi*?~m~nts.
~ c~mpone.ni.ty*pe..
. .Intended " "
Material .. .
~eCluiring " Aging Management Program
,').,
Function* 111
.. lnt~r'nal/External ** .. '.~ . 1
,." "'- /,, < I**/ **
l
{'
.Management '*/*
Closed Cycle Cooling Hardening and Loss Inspection of Internal Surfaces in Water (Int) of Strength Miscellaneous Piping and Ducting Components (FSAR SP 19.1.23)
Hardening and Loss Inspection of Internal Surfaces in Fuel Oil (Int) of Strength Miscellaneous Piping and Ducting Flexible Hoses PB Elastomer Components (FSAR SP 19.1.23}
Hardening and Loss External Surfaces Monitoring of of Strength Plant Indoor Air (Ext)
Mechanical Components Loss of Material (FSAR SP 19.1.21)
Lubricating Oil Analysis Lubricating Oil (Int) Loss of Material (FSAR SP 19.1.24)
One-Time Inspection PB Carbon Steel (FSAR SP 19.1.18)
External Surfaces Monitoring of Plant Indoor Air (Ext) Loss of Material Mechanical Components (FSAR SP 19.1.21)
Heat Exchanger (AEPS LO Cooler) Reduction of Heat Closed Cycle Cooling Transfer Closed Treated Water Systems Water (Int)
(FSAR SP 19.1.11)
Loss of Material HT, PB - Copper Alloy Lubricating Oil Analysis Lubricating Oil (Ext) Loss of Material (FSAR SP 19.1.24)
One-Time Inspection (FSAR SP 19.1.18) 7 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review
,. * ,,,,. ~ , .*. A~* in.*.g;*. E.,,ff.ect
,~-.
- . ,.Envirqnments.: , .. . , > ,' . '* * '" * **
- Requiring * , . , , :;Aging l'.lllanagemerit Program
- "Internal /External' , , Management . ,. .' . *. * , , . .
- Reduction of Heat Closed Cycle Cooling Transfer Closed Treated Water Systems Water (Int) r - - - - - - - _ _ _ , (FSAR SP 19.1.11)
Heat Exchanger Loss of Material HT, PB Copper Alloy (AEPS Radiator)
External Surfaces Monitoring of Plant Indoor Air (Ext) Loss of Material Mechanical Components (FSAR SP 19.1.21)
Fuel Oil Chemistry (FSAR SP 19.1.16)
Fuel Oil (Int) Loss of Material Aluminum One-Time Inspection (FSAR SP 19.1.18)
Plant Indoor Air {Ext) None None Atmosphere/ Weather Loss of Material (Ext)
Plant Indoor Air (Ext) Loss of Material Piping PB Loss of Material Carbon Steel Condensation (Ext)
Cracking Closed Cycle Cooling Loss of Material Closed Treated Water Systems Water (Int)
(FSAR SP 19.1.11)
Fuel Oil (Int) Loss of Material Fuel Oil Chemistry (FSAR SP 19.1.16) 8
Attachment 1 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review
'Envii:o~ments 1
' ' Intended , , ', ' '* .. ,
- Recl'uiring *~ **:. *. 'Aging 'Man~gem.~nfPtogram ComponentType
- ~ . '
- f:.~n~tion(il : . c.: Mate~iaf . .. " ln~e~n~I /External
. *: Man~g.em,en,t ,, * * . .* . . >* .* .' **
- , ... , .., ' . . J '
.:: ' " '.,'* .~ ~*'. " *. ,, ,
One-Time Inspection (FSAR SP 19.1.18)
Condensation (Int) Loss of Material Inspection of Internal Surfaces in r - - - - - - - - - - + - - - - - - - - - - 1 Miscellaneous Piping and Ducting Diesel Exhaust (Int) Loss of Material Components (FSAR SP 19.1.23}
Closed Cycle Cooling Closed Treated Water Systems Loss of Material Water {Int) , {FSAR SP 19.1.11}
Fuel Oil Chemistry Fuel Oil {Int) Loss of Material {FSAR SP 19.1.16)
One-Time Inspection {FSAR Pump PB Carbon Steel SP 19.1.18}
External Surfaces Monitoring of Mechanical Components Plant Indoor Air {Ext) Loss of Material (FSAR SP 19.1.21}
Fuel Oil Chemistry Fuel Oil (Int) Loss of Material (FSAR SP 19.1.16}
One-Time Inspection Sight Gauge PB Carbon Steel (FSAR SP 19.1.18}
External Surfaces Monitoring of Plant Indoor Air (Ext) Loss of Material Mechanical Components (FSAR SP 19.1.21}
9 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review Agi~g,'<<~ffect < . '
,,Re.quiring , ; Aging Managemei;it Progr,am Management
- - )", , ._, " ;
Fuel Oil Chemistry Fuel Oil (Int) Loss of Material (FSAR SP 19.1.16)
One-Time Inspection (FSAR SP 19.1.18)
External Surfaces Monitoring of Mechanical Components (FSAR SP 19.1.21)
Tank PB Carbon Steel Plant Indoor Air (Ext) Loss of Material Closed Cycle Cooling Closed Treated Water Systems Water (Int) (FSAR SP 19.1.11)
Carbon Steel Loss of Material External Surfaces Monitoring of Plant Indoor Air (Ext) Mechanical Components Valve PB (FSAR SP 19.1.21)
Selective Leaching Copper Alloy Closed Cycle Cooling (FSAR SP 19.1.19)
(>15% Zinc) Loss of material Water (Int) Closed Treated Water Systems (FSAR SP 19.1.11) 10
Attachment 1 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review
.. AgingEffect Envir~nm~nts. 1 * * * * *
. componenttyp~
- Req.uiting *:. . -,*~ging M~nageme~t ~rog~~*m
- . Internal/ External .: Mana9erii'ent * .. . ,,*,
'" ' '~ '.'"'*
";1 Fuel Oil Chemistry Fuel Oil (Int) Loss of Material (FSAR SP 19.1.16)
One-Time Inspection (FSAR SP 19.1.18)
Lubricating Oil Analysis Lubricating Oil (Int) Loss of Material (FSAR SP 19.1.24)
One-Time Inspection (FSAR SP 19.1.18)
Plant Indoor Air (Ext) None None Structures Monitoring (FSAR SP 19.1.31)
Atmosphere/ Weather Bolting (Structural) SS Carbon Steel Loss of material (Ext)
Loss of material (spalling, scaling)
Increase in Atmosphere/ Weather Structures Monitoring Concrete Elements SH,SS Concrete porosity and (Ext) (FSAR SP 19.1.31) permeability; loss of strength Cracking 11 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review
' " : *.Intended : ***, Envfrdnmehts. ** '~* "Aging,Effect.
component Type ... * . *. , .* (il . *.. Material ,* : ' * *. * * . * * * ,. . ~Requiring : Aging~Management Pr()gram o, -;,' ) *, :,",
- Function: *' lni~rhcil(Ext.erl'.1'1.1 .Managem,enh .. "'
'* *' ,_, _'!,, .:,:,.'..: ..; _,**. ;,\* "?.,;, ,,., *-, 'i;>~ : **; ,.,-,r... ~'",*'*;:, .. :** *- ~p.
Increase in porosity and permeability; cracking; loss of material (spalling, scaling)
Increase in porosity and permeability; cracking; loss of material (spalling, scaling)
Cracking and Buried (Ext) distortion Structures Monitoring f - - - - - - - _ _ _ , (FSAR SP 19.1.31)
Cracking; loss of bond; and loss of material (spalling, scaling)
Atmosphere/ Weather Door SH Carbon Steel f--'-(S_tr_u_c_tu_r_al~)~(E_x~t)~_ ___, Loss of material Structures Monitoring Plant Indoor Air (FSAR SP 19.1.31)
(Structural) (Ext)
Atmosphere/ Weather (Structural) (Ext) Structures Monitoring Metal Siding SH Carbon Steel Loss of material Plant Indoor Air (FSAR SP 19.1.31)
(Structural) (Ext) 12
Attachment 1 to Enclosure 1 to ULNRC-06330 Alternate Emergency Power System Aging Management Review I
,, : ' '"* ;i
, *.lnt~nded. *
\
Agin9E1'.fect. ,. '*
'l '
** * ' '11 :Material*
. * .Requiring . . .:Ag.ing Management Program*
l
( .* "* **Internal /;External .
" ..: :>**' :.,; " " .:<< ... :' .\,"
Atmosphere/ Weather Structures Monitoring Loss of material
{Structural) {Ext) {FSAR SP 19.1.31)
Concrete {Structural)
Structural Steel SH, SS Carbon Steel None None
{Ext)
Plant Indoor Air Structures Monitoring Loss of material
{Structural) {Ext) {FSAR SP 19.1.31)
Various Metals Electrical Cable Connections Not Increased Cable Connections Used for Subject to 10 CFR 50.49 EC Plant Indoor Air (Ext) resistance of (Metallic Parts) Electrical Environmental Qualification connection Contacts Requirements (FSAR SP 19.1.37)
Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Insulated Cable and Various Organic Adverse Localized Reduced insulation IN Requirements (FSAR SP 19.1.34)
Connections Polymers Environment (Ext) resistance Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements {FSAR SP 19.1.36) 13 to Enclosure 1 to ULNRC-06330 Table 2 Fire Barrier Door Aging Management Review Structures Monitoring Plant Indoor Air (FSAR SP 19.1.31)
Fire Barrier Door FB, SH Carbon Steel Loss of material (Structural) (Ext)
Fire Protection (FSAR SP 19.1.13)
(1) Intended Function Acronyms:
EC Electrical Continuity Provide electrical connections to specified sections of an electrical circuit to deliver voltage, current or signals.
FB Fire Barrier Provide rated fire barrier to confine or retard a fire from spreading to or from adjacent areas of the plant.
HT Heat Transfer Provide heat transfer.
IN Insulate (electrical) Insulate and support an electrical conductor.
PB Pressure Boundary Provide pressure-retaining boundary so that sufficient flow at adequate pressure is delivered, or provide fission product barrier for containment pressure boundary, or provide containment isolation for fission product retention.
SH Shelter, Protection Provide shelter/protection to safety-related components SS Structural Support Provide structural and/ or functional support to safety-related and/or nonsafety-related components 14 to ULNRC-06330 WITHHOLD PERRIS 2015-17 Enclosure 2 to ULNRC-06330 CD 1 Complete FSAR Text Contains Sensitive Information WITHHOLD PERRIS 2015-17 to ULNRC-06330 WITHHELD PER RIS 2015-17 Enclosure 3 to ULNRC-06330 CD2 Redacted FSAR Text WITHHELD PER RIS 2015-17