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Category:Letter type:L
MONTHYEARL-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 2024-08-07
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response L-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response L-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-022020-12-0404 December 2020 Supplement to Updated Final Response to NRC Generic Letter 2004-02 L-2020-094, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-06-26026 June 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2020-061, Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-04-30030 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements ML20015A0282020-01-14014 January 2020 NMFS to NRC, Concurrence with Interim Response to Requests for Additional Information for St. Lucie Endangered Species Act Section 7 Consultation L-2019-164, Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control2019-09-11011 September 2019 Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response2019-08-21021 August 2019 Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response L-2019-153, Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-25025 July 2019 Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-149, Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-24024 July 2019 Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-118, Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2019-06-28028 June 2019 Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2019-107, License Amendment Request - Iodine Removal System Elimination2019-05-17017 May 2019 License Amendment Request - Iodine Removal System Elimination L-2019-056, Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request2019-03-0707 March 2019 Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies2018-11-15015 November 2018 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies2018-08-17017 August 2018 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations L-77-291, Attachment a to L-77-291 Response to NRC Questions of May 24, 19772018-03-29029 March 2018 Attachment a to L-77-291 Response to NRC Questions of May 24, 1977 L-2018-040, Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2018-02-14014 February 2018 Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b L-2017-210, Updated Final Response to NRC Generic Letter 2004-022017-12-20020 December 2017 Updated Final Response to NRC Generic Letter 2004-02 L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 62017-12-19019 December 2017 License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6 L-2017-209, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-012017-11-30030 November 2017 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-01 L-2017-159, Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 02017-09-13013 September 2017 Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 0 L-2017-116, Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.52017-07-0303 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.5 L-2016-220, License Amendment Request EDG Day Tank Fuel Volume Change2016-12-0505 December 2016 License Amendment Request EDG Day Tank Fuel Volume Change L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) L-2016-153, Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes L-2016-135, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B2016-07-22022 July 2016 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents2016-07-15015 July 2016 Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents L-2016-114, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48.2016-07-0808 July 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48. L-2016-102, RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes2016-05-0606 May 2016 RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes L-2016-104, RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-05-0606 May 2016 RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle L-2016-096, Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 02016-04-21021 April 2016 Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 0 2024-06-26
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM <RlDS)
DISTRIBUTION FQR INCOMING MATERIAL 50-335 REC: ORG: UHRIG R E DOCDATE: 06/16/78 NRC FL PWR 5 LIGHT DATE RCVD: 06/19/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 RESPONSE TQ NRC LTR OF 12/15/78... FORWARDING APPLICANT"S COMPLETED QUESTIONNAIRE FOR NRC RELIABILITY STUDY OF STANDBY DIESEL GENERATOR UNITS.
PLANT NAME: ST LUCIE 3Ni REVIEWER INITIAL: X JM D I STR I BUTOR <<I NiI T I AL:
~
DISTRIBUTION OF THIS I MATERIAL IS AS FOLLOWS I RELIABILITY OF STANDBY DIESEL GENERATOR IUNITQ.
<DISTRIBUTION CODE A014) Ir f)IP li I I f
f P li -
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'OR ACTION: ORB64 BC++W/3 ENCL Ii),fc
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HANAUER++W/ENCL POWER,SYS IP5+W/ENCL,P F CLEMENSON+>W/ENCL I PDIS SER,;cBR-MC+%W/ENCL e ~
EXTERNAL: LPDR'S I , 'f I FT P I ERCEr Fl 4'<W/ENCL T IC++Ld/ENCL NS I C++W/ENCL ACRS CAT B+4W/10 ENCL e
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NRC MM405 0-1-0 UNI T'ED-STATES-NUCLEAR-REGULATORY-COMMI DDC MONTHLY ACCESSION LIST 00/01/78=~%/BO/78 FILE LEVELS DOCo DATE m~mnmmm~m~m>>>>wmm~Wmmmeem~m~mmmyoumea~mwm 50 390 TENNESSEE VALLEY AUTHORITY WATTS BAR ¹1 50 04/10/78, ACCESSION NBR>> 78103-0071
~90 E TASK NBR:
FICHE NBR C DOCUMENT SIZE: 1P+1P NOTARIZED: Y DOCKET DATE; LPDR>> Y REPORTmB .
RECP>> VARGA S A RECP AFFILI ORG>> MILLS L M ORG AFFILIA
SUBJECT:
FORWARDING ADDIDAVIT SHOWING SVC OF SAFETY, ANALYSES REPT SERVED UPON' OFFICE t NASHVILLE ~N o ET AL 0 o o NOT'A 50 04/10/78 ACCESSION NBR ~ 78104 0092 TASK NBR:
390 C
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~ NOTARIZED DOCKET 'PDR:
Y NBR.
DATE'EPORT RECP ~ RECP AFFILI ORG>> CASE E G ORG AFFILIA
SUBJECT:
ADVISING THAT NRC HAS FORWARDED TO FEDERAL REGISTFR A NOTICE OF MEETIN w I'MPLEMENTATION-OF 1 0-CFR 79~55+EQ RESEARCH FOR, PHYSICAL, PROTECTION OF IN NUC ~ PWRo REACTORS AGAINST SABOT
- 50 04/11/78 ACCESSION NBR>> 77313 0271 TASK NBR:
390 DOCUMENT TYPE>> MEMO FICHE NBR>>
DOCUMENT~-I-ZE. 1P NOT-AR I-ZED. t DOCKET LPDR NBR:
DATE'EPORT RECP>> VASSALLO-D-B RECP AFFILI ORG>> ROSS D F ORG AFFILIA UB JECT ~ SECOND-ROUN~UESTIONS ~
FLORIDA POWER & LIGHT COMPANY June 16, 1978 L-78-207 CD Director of Nuclear Reactor Regulation V7 U. S. Nuclear Regulatory Commission y Iy t.
r 'Ctl Washington, DC 20555 CXr C ~4 Qp yyy (yW ty
Dear Sir:
~%2C>
~
Cyy Re: St. Lucie Unit No. 1 (
Al
~C Docket No. 50-335 Diesel Generator Information CO The attached information is submitted in response to a letter from Karl R. Goller dated December 15, 1977.
Very truly yours,
~gyp%,
Robert E. Uhrig Vice President
~~(g5 I~g@N, REU/MAS/bb Attachment cc: Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire 78i7000gg PEOPLE .. ~ SERVING PEOPLE
I E
8 V
l}uestionnaire for HUCLEAR REGULATORY CON"lISSIOH RELIABILITY STUDY of Diesel Generator
'tandby Units'ate guestionnaire Comple ed: ~/t5/7B 0
Plant Name: Unit Ho.
Diesel manufacturer: l 2 645E4 8 16 645E4 turbo charged umber of Units: ~ (each with 1 genera'or and 2 diesels in tandem. 1 12-cylinder 1 16-cylinder) 3500
, Size Kw/Unit: Rated Speed:
Operating Hours Per Unit to Date: f'verage DIESEL GEHERATOR STATUS .
A. ~En ine:
I
- l. Problems are caused chiefly by (give estimated number) .
- a. Defective parts
- b. Insta11ation errors: ~4
- c. Failure of system to respond properly in function or sequence:
- d. Faulty adjustment:
2; Mould more stringent inspection and testing requirements Curing acceptance or preoperational tests significantly improve the di esel-generator power plant pef fol ma nce":
Yes Ho B. Startina S stems (indicate which):
Air-to-cy i inder cranking.
Air cranking motor iifn Zn9ereoll f~o4eI no D-89RH-46.
Electric cranking motor Nfr. Hodei Ho-4
- 2. If air cranking, then:
Volume 3
- Give size of starting air tank: teegth 32 ft .Diameter 30" air tank pressure 200-220 psi.
Normal standby Is pressure reducer used?
Reducer pipe size?
Yes inches.
'o x Starting air control admission valve pipe size in air piping system, 2 inches.
Hinimum air.,tank pressure for engine cranking.'110 psi.
Number of five-second cranking periods between above pressures with no tank recharging 10 starts mfn(mum I b f" i I
kp Can starting air tanks serve more than one engine?
Yes, No x ~ . .
L' v
~>4 vOf the Way uj Is- air pipe to engine from top of air tank? Yes No fran tank bottom Does starting air tank have water condensate drain?
Yes x Ho Does starting air pipe have water condensate trap and drain near engine? Yes x No Is starting air'piping horizontal? Yes x Ho w
Does it slant toward drain? Yes No x If water condensate drains are provided, then is draining:
'I a.'utomatic through float val ve? Yes x'o b.'anual b-'and valve? Yes x No
- c. ~
If manual, then is draining water condensate done:
daily?
weekly?
monthly?
before each start if manual? x no procedure?
Is dirt and rust filter provided in starting air pipe?
Yes x Ho If provided, where installed' in i before hoses to air start mot ors.
How is it cleaned? remove lu 'and filter and clean. Y strainer, How of ten and when? as needed; high del ta-P Give pipe size of filter: '2 inches..
How is it known whether filter is Flow blockage. Note:
plugged or has high oressure have redundant parallel filters.
drop?
Is starting air pipe to engine positioned:
- a. Below floor? z
- b. On the floor?
.-c. Overhead".
What is air pressure drop from air tank to engine during cranl;ing ~ 5 psi Give approximate length (nearest ten feet) of starting air pioe'or individual engine or all engines from air tank tn:
- a. Hear st engine 2O feet
- b. Furthest engine~ feet
~ ~
Diameter of starting air pipe from:
- a. Air tank to starting valve 2 inches b..At air starting valve 2 inches
- c. At engine l inches Tiose to each starter, 4 per engine, 8 per unit..
I Mhat is the primary source of power for the starting air I I
system? electrical auto start controlled by pressure switches.
Is there a duplicate and redundant motor and air compressor set? Yes x tlo 2 tanks for 2 air nu-What is'he time 'required to recharge one air tank? tors on each engine; minutes connected with check valves so that less of)l Does starting air supply system have ind pendent tank will not bleed down secondary power supply for compressor? Yes < Ho all tanks-If yes, then by:
- a. Gasoline engine?
- b. Motor dri'ven?
- c. Other? (SpecifyTVZesel driven manual start compressor.
- 3. If electric (Battery powered) cranking, then'/A a Battery charging: Continuous trickle charger.
Intermittent charging If so, how is charging requirement determined?
Time cycle Test
'ther
- b. Battery u-ed: Common Plant Individual Unit Other Starting cable (longest) size; Length: Battery to engine
s
~F1 F158 1
- 1kl '
- 1. Does the bulk tank to day tank fuel supply system (viz:
pump, motor, etc.) have redundant independent power
, supplies? Yes x No this ted emlrgeocgfue),
Does pump? Yes'o system have x hahd-o~er a
y s can gra If'yes, is this hand-operated pump and piping in immediate
'perating condition? Yes . No
- 2. Is there a water and sediment drai.n from the very bottom of the: I
- a. Bulk tank? 'es No
- b. Day tank? Yes No
- 3. Is the reqular functional fuel oil outlet'slightly above (two to three inches) the bottom of the:
- a. Bulk tank? Yes Ho
- b. Day or in"egral tank? Yes Ho
- 4. 's bottom of day tank and/or inteqral tank above all parts and piping of the enqine fuel injection systems?
Yes. Ho If yes, "Give approximate amount inches feet.
- 5. Does the engine fuel system have a fuel bleed return
~
.line xto-the fuel dav tank and/or integral tank?
Yes Ho During extended operation, such as nore than two to three hours, does the. fuel in the day tank become: (yes or no)
- a. Marm? ~es
- b. Hot. <0 (above 130'F)
Mhat is fuel oil return line size (nominal)?
- a. Pipe size 3/4 inches
- b. Tubing size inches
'o ~
s I
- 6. Do engine fuel oil filters have air bleed or vent valves.
readily accessible? Yes
- 7. How is fuel transferred from day tank to engine fuel. system?
'a. By gravityback up b.
c.
d.
Engine driven pump Electric motor driven pump
.s a manual pump
~
also provided for injection system fi'fling and/or air venting after servicing or replacement of parts in the fuel injection .
system? Yes x No If yes, is the manual pump in immediate operating condition.
Yes x Ho
- 8. T f f 1 ( .. 1,,2 A3 J -4,. ):~ll
~ I
- 9. Approx'imate bulk tank capacity, 20.o0o g'allons. eac1i 10e Typical =requency of refilling (weekly, monthly,, etc.)
ll. Typical refill (gallons) I ~
~
5 '10i1
- 1. Lube oil a ~ Type SAN40
- b. Viscosit~ PB 0 ., (1010 SSU et 100'F) 1 c- Specification number 6 'P 9 ~ (Tepaco 1463 aqd .1570).l I
- d. Oil change determined bv:~ analysis.'
Time interval: Yes, ,Ho Give interval monthly, yearly By oil analysis: Yes No
- 2. Lube oil filters are:
- a. Full flou x
- b. Bypass '.
Combination 3, Interval and/or basis for changing filter cartridoe:
t
- a. Monthly
- b. Yearly c~ By running time hours
- d. By oil analysis. Yes No
- e. By pressure drop. 'es No
- f. Does provisions exist. for changing cartridges during en'gine operation? Yes. No
- 4. Oil Pressure Monitoring See La3
't
- a. Normal operating pressure psi
,b. Alarm psi c Shutdown p si 5., Oil temperature e control:
't
- a. By standby heater in engine sump F.
- b. Heating means for maintaininq standby temperature:
Direct in oil Oil-to-water heat exchanger Other {Specify)
E. Coolin S stem - En ine Water 1; Temperature control by:
- a. By thermostat in 'Hater?
If yes, then:
Yes 'o Bypass thermostat? Yes >
thermostat? Yes No'Throttle No
~'
- b. By radiator shutter: No Automatic Manual '.
Other (give type)
Corrosion control (water additive)? Yes x Ho If yes, give chemical additive or name of compound.
Nal'cool 2000 recommended by vendor Proportion or concentration control:
By additive measurement? Yes -
No
- b. By water coolant analysis? Yes x No 3.'.Engine cooling water cooled by:
- a. Radiator'? x
- b. Heat exchanger from sea, river or other water?
c.. Other? (give type) ion)
Engine cooling'ater temperature-monitoring a 'Standby temperature lid Isn'F
- b. Horaal operating temperature 16O-ISO 'F
- c. Alarm temperature H/A ~F ow surge tank level at 6".
- d. 1 1 p e5 'F
- e. =Mater circulation during standby:
syphon x . (natura 1 c i rcui at pump
- 5. Mater Pressure Monitoring: 'es x No
- a. Al arm no Local indication.
- b. Shutdown
- c. Both
~ ~
0
- 6. Water temperature Sensor Position:
- a. - In piping from engine x
- b. In engine piping c.. In engine direct
- 7. Water surge or supply tank in system. Yes x Ho If yes, then bottom connected to:
a.
b.
c.
d.
Mater Top
's pump suction?
of system? Yes Both of above? Yes bottom of surge tank
'o Yes x Ho Ho above top of engine system? Yes Ho
- e. Does engine. have constant air bleed from 'top of engine water piping to surge or supply tan!<?
Yes > Ho
- f. Give size of bleed or vent .line, . 8 . inches.
" NNoN<<<<h<<an"l
- g. Nanual air bleed'nly? Yes F.. Governor - S eed Control tianufacturer
'(P Hydraul i c Type or code such as EGB-35, LSG-10, etc.) EGB-1OP Automatic load sharing? Yes Ho
=
- l. Is compensation or stability control and/or speed of response manually-adjustable? Yes Ho x If yes, ad,iusted by:
Eye an3'sas 0
'~
- b. "Test and spec'ifica ion?'..
Other? (Speci fy)
- 2. Engine - generator normal shutdown or stopping means and method.
Y
~ ~ a I
Is the engine stopped:
- a. Manual ly? Yes x Ho If yes, then:
Directly at engine? Yes. Ho Through local control panel? Yes No Manually from control room is the normal method.
- b. . Automatically through the controls in the contr'ol I room? Yes l'lo Manual. controls in control room initiate.shutdown.
a
.. c. By setting governor to "fuel-off"'position?
Yes. x Ho a
'd. By over-.ride of governor settings and control position directly to fuel injection pumps?
Yes Ho x
- e. =
Other means. Describe briefly.
aa
- 3. =
When engine is stopped, is fuel control'in:
a
- a. Full fuel or maximum fuel position'?
- b. Full off or no fuel position?
- c. Intermediate?
- d. Random? II l1
~
a t (If not consistent and typical in above, then. give the usual.).
a
- 4. When starting from the standby condition after shutdown for at least 24 hours, give number of seconds from-start-, a to-crank to full fuel or maximum fuel position of governor and fuel control, l , seconds aa a ~
~ s"
,~
G. Governor Overspeed (shutdown)
- 1. Soeed sensing?
- a. Electrical >200rpm
- b. Flyball <200~rpm mechanical control if electrical control lost)
- c. Other (Specify)
- 2. Fuel shutoff force generated by:
C
- a. Spring? .
- b. Air?
- c. Hydraulic?
- d. Electrical?
- e. Other? (Speci~fy
- 3. Overspeed. sensing setting? (in terms of full speed)
- a. .11M P'(116K) .
- b. 110%,
c.. Other~Specify)
, ~
Is overspeed tripping set point tested periodically?
Yes Ho If yes, then how often? '
(yearly, monthly, etc.)
H. l. Generator" s~ifr.
s Electric Machinexgodel No. Series 700 Single bearing or two bearings? Two Does generator have damp r windings? Yes Ho v'oes
- 2. genera or have any obvious fault or difficulty?.
Yes tJo x.
'o Is'roblem repetitive? Yes If yes, th n describe briefly.
~0
~ I I. Exciter and Volta e Regulator Exciter Manufacturer: Electric Machineryfode] CUT static exciter with SCR regulator..
v Ty'pe: Rota tinq Static If rotating drive? Direct Belt or Chain DC with field control
, Brushless with rectifier 2.
3.
Voltage Regulator:
Type:.'echanical.
Are
'tatic Manufacturer pdectcsc Naoldn~lodel paralleled units of automatic load sharing control
'anm ae 1 of fully automatic type?'es No N/A I
If yes, has any obvious influence or interrelationship been noted between the stability. and response time of-the engire governor and the stability and voltage control of the generators? Yes No
.Have engine governor 'and voltage regulator/exciter adjusts ents been made on the site or under any con-ditions since any of the uni ts have been placed in .
service? Yes > tlo If yes,- by means of what tests and what standards?.-"
rame or very brief description.
.'ive manual verified by test runs=.
- 5. If any difficulties have occurred, give approximate number of problems. .N/A
- a. Components 4ii ing c., Ot'ner (damage in service or dropping of miscellaneous hardwa, e into switchboard, etc.)
1
~ ~
-l 3-'.
Parallelin: En ine-Generator Units N/A (Do not parallel the diesel generators)
- 1. Do all units consistently have the proper voltage output?
Yes No
- 2. Do all units automatically'hare both the "real" or in-phase load and also the reactive load reasonably well? Yes Ho
- 3. At the same Kw load, are both the field and the armature line currents of the several units consistently close to the same value?. Yes" No
~ ~
If no, approximate percent difference.
- 4. Synchronizing
- a. In automatic synchronizing do circuit breakers close
,immediately after reaching full synchronous speed?
Yes Ho
- b. If "no" above then, does speed of some units drift slowly while failing to synchronize and close circuit breakers?
How many seconds?'ccasionally Always Never K. Switch Gear and Electrical Con (other than exciter/
voltage regulator
- l. If any difficulties have occurred, then give approximate number of problems.-
- a. Components '4
. b. Mirinc
- c. Other '(damage in service or dropping of miscellaneous hardware into switchboard, etc. I
- d. Desi gn concept faul ts. That i s, does the swi tch qear and its controls perform the proper functions and in proper sequence and timing.
'2. a. Do the on-site diesel generator units and related support equipment have any storage battery power system's forany service whatsoever? Yes' No
- b. Identify each storage battery power system associated with the on-site diesel generator unit and.its function. Re: FSAR Section 8.3.2;l.
=.
M <<<<<<<<
- c. Does each system identified above adequately fulfill the service requirements for which it is intended?
Yes P No f
I no, briefly describe.
<<'. Is there a DG battery maintenance program? Yes / No L. Safet Shut downs I
Give safety shut down settings compared to equilibrium operating condi.tions'.-
- l. Engine and generator speed. Give rpn or hertz:
<<: << rpm or" 60 Hz
- b. Qverspeed shutdown setting
- 2. Engine cooling water (see E..4}
- e. Equilibrium 160-190 F
- b. Alarm None F
- c. Shut d~QHi1 06 F
- 3. Lube oil pressure (.see D.4)
- a. Equi l ibriun 25-2g .psi None psi (low level at 6" in oil sump)
- c. Shut doun 1> psi
4 4
- 4. Lube oil, temperature
- a. Equilibrium 125-155 'F in standby..
- b. Alarm None F
- c. Shutdown None 'F
- 5. Indicate all other protective interlocks (give name and;)
a.. Usual or proper condition (see (b))
Shutdown condition ener " d2.fferential, generator o~~ent,.reverse power flaw to generator, loss of generator ezcitatio
- 6. a. Mhat source of power is provided to operate alarms
~
, and shutdown controls? (See 6.2) 125V DC busses lA 8 1B
- b. Do the generator units automatically shutdown in case of the electrical po~er loss to its control system? Yes No / Output breaker stays closed; governor shifts to complete hydraul-ic control; regulator is powered from generator output.
M. Emer enc or Alert Conditions Are all safety shutdown and safety interlocks bypassed during emergency condi tions? Yes No 2., If "no" above, then which'are not bypassed. Name items.
Engine overspeak and generator.ddifferential.
4 3.= For each interlock rot bypassed is coincident logic used? Yes No If yes, is it testab1e'? Yes No N. Haintenance
- l. Does plant have regularly scheduled maintenance pro-1 . 4 id' 1 gill 1 If so,. return copy of these procedures with questionnaire.
P'
~
~ ~
c
~ s
~ ~
s
- 2. When need for minor adjustments obviously exists, then:
- a. Is remedial action taken immediately or at earliest practical opportunity? Yes < Ho
- b. Is remedial action taken only at periodic- pr esch'eduled or prograrmied tines and conditions? Yes No x
- c. For best. performance record which of above appears better:
immediate or early action?
as scheduled only?
- d. Must permission for minor maintenace be obtained from sone higher out-of-plant authority? . Yes No
- e. Is maintenance referred to above allowed and encouraged?
, Yes ~ t>o In periodic surveillance tests, simulated alert standby tests, etc., is the criteria "pass/not.pass" the t st used? Yes x )Jo Per Technical ..specifications s
- g. Is there a conscious continuing policy to'.detect and remedy marginal conditions or imminent trouble: for, examples: lube oil pressure shutdown only two to five psi below operating- pressure or, perhaps overspeed governor setting only one or two percent above starting speed surge or etc.? Yes > No
- h. Are efforts to remedy 'marginal or questionable conditions as mentioned above encouraged by plant management?
Yes x No Are remedial steps on items similar to the above taken or allowed when the unit has started and operated satisfactorily within specified limits or conditions?
Yes No
- 0. Startin 'Condi ions Give startin g or necessar crankin g time as ex p erienced.
a.,'Starting tine per specification 10 seconds from start signal
- b. usual starting time
- c. Maximum starting time observed ~~
9.5 seconds seconds to breaker closur
Give usual time intervals as follows:
- a. Time from start-to-crank to first firing of any cylinder . .& seconds
- b. Time from start-to-crank '
to approximate full firing of all cylinders. - 7 seconds
- 3. Give maximum speed surge when starting; use both tachometer and frequency meter if possible.
- a. Usual conditions UN rpm Hz
- b. Itaximum observed IIII rpm
~
.- 61.5 Hz
'During a surveillance test, give time from start-to-crank to when steady synchronous speed is attained and maintain d.
- a. Usual 9-9.5 seconds
- b. Maximum mm seconds
.c, As specified IO seconds.
~
- 5. Giv'e briefly the mbst troublesome problems in s'tarting.
a., Host troublesome Turbochar er roblems durin start.
- b. Next to most troublesome N A'.
Air Cleaner or Air Filter - Combustion Air
. l. Combustion air source: taken from engine room or inside the building, or from outdoors'?,
- a. Indoors
- b. Ou doors
~
s a
- 2. Give, type and make of air cIeaners or air filters:
- a. Oil bath Hake
- b. Oil wetted screen Hake
- c. 'aper )(I250 Hake Stewar - ievenson
- d. Other t1ake
- e. Precleaner: Yes . No
- 3. Excessive air flow restriction and servicing need determined by?
- a. Instrument such as:
manometer If other give type
- b. Personal judgemen". by appearance, etc.
- c. 8y smoking exhaust d.. Time schedule ever 3 ears
- e. 'ther (Specify
- 4. Are climatic extremes normally experienced such as:
'. Air heavily no..
logged with water mist,. high humidity
'es and low temperhfure? Yes Ho:-.
- b. Blowing sand and dust'? Yes x Ho 'c(metimes
- c. Blowing snow (blizzards)'? Yes No d.
/
0 her-Name g
- 5. Are climatic extremes potentially possible such as:
yes . y@s
- a. Air heavily loadpg with water mist,'high humidi'ty and low temperature? Yes .
No
- b. Blowing sand and dust'?'es x No
- c. Blowing snow (blizzards)? Yes Ho x Other-Name
'd.
(}. Tem erature Conditions
- l. Ambient outside hottest F'. rarely.
- 2. Ambient'utside coldest 2-3 tares pez year
- 3. Engine-generator room hottest 'N F.
- 4. Engine-generator room coldest 30 'F. 2-3 times per year
- 5. Inside switch gear hottest UN
~ a
I s ~
~ ~ ss ~
~ > ~
R.-, 0 erator gualifications,(as presently exists, and suggested I
minimums if different
- 1. Ninimum education required (check)
~Exis tin ~Su asst d
- a. High School . =
x
- b. Trade School
- c. Technical'School
- d. No minimum
- 2. Minimum Years of operating experience (diesel electric generator)
Existlna ~Su aested
- a. '0-3
- b. 3-6
- c. 6-10
- d. '0-15
- 3. Operator training
~Exi s ti n S~uaes ted
- a. Nil i tary~ s~~s
~~8
- b. Industrial
- c. On-the-job I
- d. Combination of a, b, and c (indicate ~hich)
- 4. Licensing required Exist'Ina ~Su seated
- a. State
- b. Federal
- c. Utility or self
- d. Hone
~ d S hag
~
S. Are any foreicnn gases such as propane, freon, halon, 'carbon dioxide, etc. stored in the: Diesel Engine room?
Yes Ho < or adjacent buil dings? Yes No If yes,. (other than hand portable fire extinguishers), th n identify gases and give approximate tank size.
3 Gases Volume (ft )
T; Does control system automatically bypass, in emergency starting, any engine temporarily out of service for .
maintenance? Yes No If yes, then how many failures to bypass have occured?
U. Does the control system automatically override the test mode under emergency conditions? Yes sc No V. Have repetitive mechanical failures occurred in ahy component part or subJsst m of the engine, generator, or switch gear, etc.?
Yes iso.
Turbo-charger', loss of lubricati,on to If ves, then which part or subsystem?
How many failures?
There are 4 ttur-I unit Give nature of failure.
(Py desi~). at 20Q rpmbut main oil pump had not developed pressure.
Desi chan e 'emented ~
portable qccurance 335-.77-.42,. follcmup report Nl< of 5/15/78 W. Mould by Give brief reasons for the answer.
No Me
~
periodic (yearly or other) evaluation and/or testing "outside experts" contribute significantly to the diesel-generator reliability? Yes have sufficient knowledge Ihd I I I
~h- bv.
h I dd=h I I lddd
d~
I "g1
~
~
C ~
4 v
X. l. Give the accumulated time-load operating record for each diesel-generator unit from installation to the present (Running Hours):
I Preoperational test Date '-75 Engine : Surv. Testing 5 : Emergency : Total .:
- Serial Ho. : Naintenance Hrs. : and Other : Hours-No Load: Loaded : Service Hrs. :
10 : ~161 186
~-
1B > 10 ' ~1)4 ~ 'v 15 C
. 149 ~
v ~
C
.d.
,"(OTE: Total Hours were read rough estimates.
1 111 1 1d id '1off hour 1
me er . emaining n m are
- 3. Give the projected or planned time-load:operation for each diesel-generator unit during the rlext 12 months.
- Surveillance 8 Emergency: '.otal
- Maintenance Hrs. : ~
and other : Hours Service Hrs.
~36 0 .~36 Provide the followinq summary of the periodic surveillance testing experience:
- a. Starting date of surveillance testing (OL date) 3-1-76
- d. 1 di servi<
c..
<<1 Total number of surveillance tests performed80*
dd11'~
~
1 11 failure to start 4 (2 op. ~failure to ii .d accept load 1- u~uld not reach fQll e to 1 1 1- /did failed conditions probl gex' charger
.e. Supply a copy of the surveillance test procedures with th)s
.'ompleted questionnaire.
C
~ ~
.Additional Comments Y. General Su estions Briefly give constructive criticism or suggestions as to improvement in reliability of'he diesel generators. These remarks may cover tests, maintenance, practices, order's, policy, adjustments, etc.