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Category:Report
MONTHYEARML23333A0172023-11-27027 November 2023 Attachment I - Chin - the Cooling Canal System at the FPL-Turkey-Point Power Station ML23333A0142023-11-27027 November 2023 Attachment F - Groundwater Tek Inc - Peer Review Study Final-1 ML24012A0422023-11-16016 November 2023 FAQ 23-03 Turkey Point IE01 Proposed NRC Response ML23265A5512023-09-22022 September 2023 Enclosure 3: WCAP-18830-NP, Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-038, Emergency Response Data System (Eros) Changes2022-05-17017 May 2022 Emergency Response Data System (Eros) Changes L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-022, Updated Conditions of Certification Report2022-02-14014 February 2022 Updated Conditions of Certification Report L-2021-182, Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions2021-09-16016 September 2021 Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions L-2021-069, Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds)2021-06-24024 June 2021 Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds) IR 05000250/20200112020-07-23023 July 2020 NRC Inspection Report 05000250-2020011 and 05000251-2020011 and Investigation Report 2-2019-011; and Apparent Violation Final L-2020-073, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping2020-04-13013 April 2020 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-204, Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification2019-11-25025 November 2019 Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds L-2019-054, Baffle-Former Bolts Predictive Evaluations2019-03-13013 March 2019 Baffle-Former Bolts Predictive Evaluations ML19072A1622019-03-0505 March 2019 National Park Service, Southeast Regional Office, Comments Dated March 5, 2019, on Turkey Point Nuclear Generating Units 3 and 4 Preliminary Draft SEIS Regarding Subsequent License Renewal ML18353A8352018-12-31031 December 2018 Biological Assessment for the Turkey Point Units 3 and 4 Proposed Subsequent License Renewal ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-173, Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program2018-09-21021 September 2018 Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program ML18254A3412018-09-11011 September 2018 Fish and Wildlife Service'S List of Migratory Birds Near Turkey Point ML18227B5212018-08-15015 August 2018 Submit Attachment a, Annual Hourly Percent Frequency of Vertical and Horizontal Stability Categories by Wind Direction and Wind Speed ML18227A2902018-08-15015 August 2018 Submit Report Contains Official Summary of Startup Physics Tests, Unit 4 Cycle Iii. the Tests Were Conducted in Accordance with Operating Procedure 0204.5, Startup Sequence After Refueling L-2018-098, Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.462018-04-18018 April 2018 Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.46 L-2018-054, Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/172018-02-16016 February 2018 Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/17 L-2017-148, Special Report - Accident Monitoring Instrumentation2017-08-11011 August 2017 Special Report - Accident Monitoring Instrumentation L-2017-123, Special Report - Standby Steam Generator Feedwater Pumps Inoperable2017-06-29029 June 2017 Special Report - Standby Steam Generator Feedwater Pumps Inoperable L-2017-124, Flooding Focused Evaluation Summary2017-06-29029 June 2017 Flooding Focused Evaluation Summary L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 L-2016-226, NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information2016-12-20020 December 2016 NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information L-2016-058, Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis2016-03-23023 March 2016 Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis ML16013A4722016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task L-2015-313, Special Report - Accident Monitoring Instrumentation2015-12-18018 December 2015 Special Report - Accident Monitoring Instrumentation L-2015-137, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2015-04-22022 April 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments ML15054A0372015-02-23023 February 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Turkey Point Nuclear Generating Stations, Units 3 and 4 ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal L-2014-233, Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I)2014-07-22022 July 2014 Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I) L-2014-085, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 2023-09-22
[Table view] Category:Technical
MONTHYEARML23333A0142023-11-27027 November 2023 Attachment F - Groundwater Tek Inc - Peer Review Study Final-1 ML23333A0172023-11-27027 November 2023 Attachment I - Chin - the Cooling Canal System at the FPL-Turkey-Point Power Station ML23265A5512023-09-22022 September 2023 Enclosure 3: WCAP-18830-NP, Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-022, Updated Conditions of Certification Report2022-02-14014 February 2022 Updated Conditions of Certification Report L-2021-069, Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds)2021-06-24024 June 2021 Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds) L-2020-073, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping2020-04-13013 April 2020 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds L-2019-054, Baffle-Former Bolts Predictive Evaluations2019-03-13013 March 2019 Baffle-Former Bolts Predictive Evaluations ML19072A1622019-03-0505 March 2019 National Park Service, Southeast Regional Office, Comments Dated March 5, 2019, on Turkey Point Nuclear Generating Units 3 and 4 Preliminary Draft SEIS Regarding Subsequent License Renewal ML18353A8352018-12-31031 December 2018 Biological Assessment for the Turkey Point Units 3 and 4 Proposed Subsequent License Renewal ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18227B5212018-08-15015 August 2018 Submit Attachment a, Annual Hourly Percent Frequency of Vertical and Horizontal Stability Categories by Wind Direction and Wind Speed ML18227A2902018-08-15015 August 2018 Submit Report Contains Official Summary of Startup Physics Tests, Unit 4 Cycle Iii. the Tests Were Conducted in Accordance with Operating Procedure 0204.5, Startup Sequence After Refueling L-2018-098, Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.462018-04-18018 April 2018 Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.46 L-2018-054, Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/172018-02-16016 February 2018 Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/17 L-2014-085, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14002A1602014-02-0606 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14029A2522014-01-29029 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Turkey Point Nuclear Plant, Units 3 and 4, TAC Nos.: MF0982 and MF0983 ML13213A1902013-07-0909 July 2013 Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 3. L-2013-198, Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 4.2013-07-0909 July 2013 Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 4. L-2013-087, Flood Hazard Reevaluation Report in Response to 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.1. Part 2 of 22013-03-11011 March 2013 Flood Hazard Reevaluation Report in Response to 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.1. Part 2 of 2 ML13095A1962013-03-11011 March 2013 Flood Hazard Reevaluation Report in Response to 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.1. Part 1 of 2 L-2012-417, Flooding Walkdown Report FPL061-PR-001, Rev 0, in Response to the 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding2012-11-20020 November 2012 Flooding Walkdown Report FPL061-PR-001, Rev 0, in Response to the 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding L-2011-190, WCAP-17070-NP, Revision 1, Westinghouse Setpoint Methodology for Protection Systems, Turkey Point, Units 3 & 4 (Power Uprate to 2644 Mwt - Core Power), Attachment 2 to L-2011-1902011-06-30030 June 2011 WCAP-17070-NP, Revision 1, Westinghouse Setpoint Methodology for Protection Systems, Turkey Point, Units 3 & 4 (Power Uprate to 2644 Mwt - Core Power), Attachment 2 to L-2011-190 L-2011-032, WCAP-17094-NP, Rev 3, Turkey Point, Units 3 and 4 New Fuel Storage Rack and Spent Fuel Pool Criticality Analysis, Attachment 2 to L-2011-0322011-02-28028 February 2011 WCAP-17094-NP, Rev 3, Turkey Point, Units 3 and 4 New Fuel Storage Rack and Spent Fuel Pool Criticality Analysis, Attachment 2 to L-2011-032 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 2; Renewed Facility Operating License and Technical Specification Proposed Change Markups2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 2; Renewed Facility Operating License and Technical Specification Proposed Change Markups ML1035601802010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 04; Appendix C, List of Key Acronyms ML1035601832010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 07; Supplemental Environmental Report L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 08; Cameron/Caldon Ultrasonics Engineering Reports2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 08; Cameron/Caldon Ultrasonics Engineering Reports ML1035601842010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 08; Cameron/Caldon Ultrasonics Engineering Reports L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 07; Supplemental Environmental Report2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 07; Supplemental Environmental Report L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 06; Summary of Regulatory Commitments2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 06; Summary of Regulatory Commitments ML1035601822010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 06; Summary of Regulatory Commitments L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix C, List of Key Acronyms2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix C, List of Key Acronyms L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix B, Additional Codes and Methods2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix B, Additional Codes and Methods ML1035601792010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 04; Appendix B, Additional Codes and Methods L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix a, Safety Evaluation Report Compliance2010-12-14014 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix a, Safety Evaluation Report Compliance ML1035601782010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 04; Appendix a, Safety Evaluation Report Compliance ML1035601742010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes 2023-09-22
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3.7 EMERGENCY LIGHTING 3.
7.1 INTRODUCTION
The emergency lighting facilities at the Turkey Point Plant provide illumination in areas needed for operation of safe shutdown equipment, as well as access and egress routes thereto in the event that normal lighting is unavailable. In addition, the emergency lighting facilities have been designed to provide for personnel safety, based on prudent engineering judgement.
3.7.2 DESIGN BASES The design of the Emergency Lighting facilities is based on the guidancetpequirements set forth in 10 CFR 50 Appendix R, section III.J and Appendi3 A to BTP 9.5-1. The following are specific design criteria:
a) Lighting shall be provided for personnel safety and general access/egress.
b) sealed beam lighting units with eight hour minimum battery power supplies shall be provided for hot standby equipment requiring local operator action, and access/egress routes thereto.
c) Dedicated portable sealed beam battery-operated lighting units, stored in fire cabinets outside the containment, shall be provided for containment entry if operation of valves in the containment is necessary to achieve or maintain cold shutdown.
d) The control Room Emergency Lighting shall be available and of sufficient intensity for safe shutdown from the control Room with a fire in a single fire area coincident with a loss of offsite power.
e) Dedicated portable battery-powered lighting units with an eight hour nominal rated battery supply shall be provided in designated storage lockers. These lights are to provide required lighting for access, egress and manual actions.
3.
7.3 DESCRIPTION
The battery pack emergency lighting facilities are wired to the plant electrical lighting system and automatically maintain the battery in a ready state. In the event of a loss of AC power, the unit automatically turns the emergency lights on. upon restoration of power the unit automatically turns off the emergency lights and places them on charge.
Equipment and access routes are illuminated to enable the operator to perform specific actions and negotiate the paths safely. In addition, other emergency lighting units are installed for personnel safety, based on prudent engineering judgement, and are not associated with Appendix R requirements.
see Reference 20 for a tabulation of Appendix R - required emergency lighting units. Refer to Figures 9.6A-12 through 9.6A-15 for the locations of emergency lighting.
The emergency lighting units are installed in accordance with the vendor's instructions and the applicable design documents. The units are seismically mounted where required.
9.6A-100 Rev. 8 7/90 Information in this record was deleted R inaccordance with t efreedom of Information Act, exemptions
Two independent sources of emergency lighting are provided for the Control Room. These emergency lights are battery-packed and will operate for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and will ensure adequate lighting in areas required for safe operation. Each train of control Room emergency lighting is powered from an independent battery source which meets the separation requirements of Appendix R Section III.G.2. cables for the two independent lighting systems are routed through separate fire areas up to the control room fire boundary.
Four dedicated portable emergency lights are provided in a fire locker for use in either containment to facilitate containment lighting, if required, to reach cold shutdown.
Dedicated portable emergency lighting units are provided in designated storage lockers to use for access, egress and manual actions. Fixed emergency lights are provided at these manual action stations.
3.8 COMMUNICATIONS 3.
8.1 INTRODUCTION
Communication necessary with regard to fire protection at Turkey Point Units 3 and 4 is provided by the alternate shutdown and the fire brigade communication system.
3.8.2 DESIGN BASES The design of the communications systems is based on standard good practice for communications systems and the guidance contained in Appendix A to BTP APCSB 9.5-1. This design guidance is summarized below:.
a) Communication systems shall be adequate to coordinate fire fighting and safe shutdown activities.
b) _ Communications systems should be protected from exposure fire damage.
3.
8.3 DESCRIPTION
- 9. 6A-101 Rev. 10 7/92
- X 3.
9.1 INTRODUCTION
The design of the plant and the strict control of combustibles considerably reduce the possibility of a fire that cannot be extinguished quickly by the on site fire brigade. Nevertheless, in case offsite assistance is ever needed, appropriate mutual aid agreements have been made.
3.9.2 DESIGN BASES The design bases guidance for coordination with the local fire departments is provided in Appendix A to BTP-APCSB 9.5-1. This guidance is summarized below.
a) The public fire department response should be considered in the overall fire protection program.
b) '
c) coordination with the local fire department should include training of the local fire department in precautions that need to be-taken when fighting fires on nuclear Plant sites such as radiation protection-of -
personnel and other special hazards.;
3.
9.3 DESCRIPTION
- _lf
/
9.6A-102 Rev. 16 10/99 1
The 1-1/2 inch drain lines can accommodate a gravity induced flow rate in excess of 14 gpm. This flow rate exceeds the maximum expected leakage rate of 10 gallons per year for each pump (Reference 33) and exceeds the 10 gpm flow rate expected from an RCP lube oil lift pump discharge line break.
An exemption was granted from that portion of 10 CFR 50, Appendix R section III.0, which requires an oil collection tank to be capable of containing the lube oil inventory of all three reactor coolant pump motors. (Refer to section 4.0 of this Appendix.)
.3.11 FIRE RATED ASSEMBLIES - BARRIERS 3 .
11.1 INTRODUCTION
Fire barriers at Turkey Point Units 3 and 4 are provided as part of the protection to ensure that the function of one set of redundant safety-related equipment necessary to achieve and maintain hot standby conditions remains free of fire damage. Fire barriers provide a means of limiting fire travel by compartmentalization and containment. In some cases written evaluations approved by a Fire Protection Engineer may be kept on file to demonstrate acceptability of a fire rated assembly or barrier. (Reference NRC Generic Letter 86-10 paragraph C.)
3.11.2 WALLS, FLOORS AND CEILINGS 3.11.2.1 Design Bases a) Pursuant to Appendix R section III.G.2(a), walls, floors and ceilings separating Fire Areas shall be fire barriers with a minimum rating of three hours as defined by ASTM E-119 (e.g. six inch solid concrete or greater, 8 inch concrete filled concrete block or greater; Thermo-lag thickness per engineering design output).
b) walls, floors and ceilings installed as fire barriers shall be designed to maintain the class of the structure (refer to FSAR Appendix 5A) and to preclude damage to nearby safety related equipment.
c) FPL requested exemptions (Reference 4) from the NRC for fire rated doorsand dampers in exterior wall penetrations in the Auxiliary Building, control Building, Unit 3 Diesel Generator Building and Switchgear Buildings. The NRC determined (Reference 6) that since the exterior walls in question did not separate redundant safe shutdown equipment and no fire hazards existed within 50 feet of the buildings, no deviations were required. Therefore, exterior walls do not require openings to be protected by 3-hour rated fire doors, fire dampers or penetration seals provided those walls do not serve to separate redundant safe shutdown equipment or circuits and no exterior fire hazards exist within 50 feet of the building.
3.11.2.2 Description The plant is divided into fire zones, which are grouped into Appendix R Fire Areas. Fire Areas are separated from each other by rated fire barriers.
These barriers are shown on Figures 9.6A-8 through 9.6A-11. The composition of these barriers is described for each fire zone in section 4.0 of this Appendix.
9.6A-104 Rev. 17
- . i Floor slabs which rest on soil foundations and earthbound walls may be designated as fire barriers but due to their underground nature will not be required to have a specific fire rating.
The unit 3 or unit 4 containment wall forms a portion of the fire barrier for several fire areas. Although the containment wall is not a tested configuration for fire barriers, its construction is of such substantial integrity as to justify its use as a three hour rated fire barrier.
9.6A-104a Rev. 15 4/98
till A4b Ac Fire Protection Systems:
.4d smoke Venting:
smoke removal may be accomplished through the personnel doors with portable smoke ejectors available onsite for fire brigade
- use.
4.5.2 APPENDIX R EXEMPTIONS No exemptions were requested for this fire area.
FIRE HAZARD ANALYSIS FOR FIRE AREA T 4.T DESCRIPTION OF FIRE AREA rea T is the Unit Rod Equipment Room, located on the elevation of the The area is a single zone area 7FoMprlsed of Fire Zone beg Pertinent f zone details are provided below. L Fire Area T and the essential equipment and cables within have been evaluated with respect to protection and separation criteria of Appendix R Section III-G.2 to assure that the ability to safely shut down the plant is not adversely affected by a single fire event.
9.6A-195 Rev. 16 10/99
A . t 4.T. I FIRE ZONE 63 -. UNIT 3 REACTOR CONTROL ROD EQUIPMENT ROOM IE7 Fire Zone 3ibounded on the fionn-seil-ina and walls by 'a3-hourraefie e
LIa 4.T.1.1 Essential Equipment within Fire zone 63 See Appendix R Essential Equipment List, Reference 15.
4.T.1.2 Fire Zone 63 - combustible Loadings SORCE QUANTITY
-7 4.T.1.3 Fire Control
.4a Physical Containment:
Fire Zone Boundary L1 6/i I
.4b - Detection: - -
.4c Fire-Protection Systems:
- 1. Primary . .
- 9. 6A-196 06/20/2001
- 2. seconday
.4d smoke Venting:
smoke removal may be accomplished through the personnel doors with portable smoke ejectors available onsite for fire brigade use.
4.T.2 APPENDIX R EXEMPTIONS See Section 3.11.2.1 c)
FIRE HAZARD ANALYSIS FOR FIRE AREA U 4.U DESCRIPTION OF FIRE AREA Fire Area U is the Unit 4 4160V Switchgear 4B Room, located on the elevation. The area is a single zone area comprised of Fire Zone 6 Pertinent fire zone details are provided below.
Fire Area U and the essential equipment and cables within have been evaluated with respect to protection and separation criteria of Appendix R Section III-G.2 to assure that the ability to safely shut-down the plant is not adversely affected by a single fire event.
4.U.1 FIRE ZONE 67 - 4160V SWITCHGEAR 4B ROOM LVgj Fire Zone 67 is bounded on the ceiling and-all walls by a 3-hour-__rae 4.U.1.1 Essential EpuiDment within Flre Zone 67 see Appendix R Essential Equipment List, Reference 15.
4.U.1.2 Fire zone 67 - combustible Loadinas SOURCE QUANTITY Q- (BTU)
I Ž1/
- 9. 6A-197 06/20/2001
4.U.1.3 Fire control
.4a Physical Containment:
Fire Zone Boundary N -
4b lk4
.4c Fire Protection Systems:
- 1. Primary .
~I
- 2. ssecondary
.4d smoke Venting:
No positive exhaust is provided in this Fire Zone. Smoke may be vented through personnel doors with portable smoke ejectors available onsite for fire brigade use.
4.U.2 APPENDIX R EXEMPTIONS see Section 3.11.2.1 c)
FIRE HAZARD ANALYSIS FOR FIRE AREA V .1 4.V DESCRIPTION OF FIRE AREA _ L4q Fire Area V is the Unit 4 416V Switchgear 4A Room, located on the L elevation. The area is a single zone area comprised of Fire Zonef Pertinent fire zone details are provided below.
9.6A-198 Rev. 15 4/98
4' 4.LL.2 APPENDIX R EXEMPTIONS No exemptions were requested for this fire area.
FIRE HAZARD ANALYSIS FOR FIRE AREA MM 4.MM DESCRIPTION OF FIRE AREA
,ire ,M is , t 3 and 4 control. Room located on th levation of heTheaarea is comprised of fire Zones 1 and 97.
Pertinent fiFre zo-ne-6tails are provided below. Refer to Section 5.0 of this Appendix for a discussion of the Alternate shutdown capabilities provided for this fire area.
Fire Area MM and the essential equipment and cables within have been evaluated with respect to protection and separation criteria of Appendix R Section III-G.2 to assure that the ability to safely shut down the plant is not adversely affected by a single fire event.
4.MM.1 UNITS 3 AND 4 CONTROL ROOM MECHANICAL EQUIPMENT ROOM -
Fire Zone 97 is bou ned on the floor and walls by a 3-hour rated fire barrier, with the exception of the West and South walls which contain_ on-rated Qgmggs.,
Equipment in this zone includes 3 Air Handling Units and the -
filter, unit.
4.MM.1.1 Essential EquiDment within Fire Zone 97 see Appendix R Essential Equipment List, Reference 15.
4.MM.1.2 Fire Zone 97 - combustible Loadings SOURCE - UANTITY - BTU) -
I7 4.MM.1.3 Fire
.4a Physical Containment:
Fire Zone Boundary walls North:
South:
East:
West:
9.6A-227 06/20/2001
.4b ection. 7{
.4c Fire Protection Systems:
- 1. Primary --- --- ~ ~ -
- 2. Secondary
.4d smoke Venting:
Portable smoke ejectors available onsite may be used to vent smoke.
4.MM.2 FIRE ZONE 106 - UNITS 3 AND 4 CONTROL ROOM COMPLEX VI Fire Zone 106 is bounded on the ceiling, floor and all four walls by a 3-hour rated fire barrier. An exception to this barrier integrity includes non-rated Door D106-2. However, this door has an equivalent 3-hour fire rating. Equipment -in this zone includes the Unit 3 and 4 control and monitoring equipment.
4.MM.2.1 Essential EQuipment Within Fire Zone See Appendix R Essential Equipment List, Reference 15.
4.MM.2.2 Fire Zone 106 - combustible Loadings SOURCE UATITY (BTU) 9.6A-228 06/20/2001
4.MM.2.3 Fire control
.4a Physical Containment:
Fire Zone Boundarv I
4b
.4c Fire Protection Systems:
- 1. Primar -
- 2. Secondary U
.4d Smoke Venting:
ventilation in this fire zone is provided by Exhaust Fans EF-9 and EF-20. Also, portable smoke ejectors are available onsite for fire brigade use.
4.MM.3 FIRE ZONE 106R - UNITS 3 AND 4 CONTROL ROOM ROOF - *I Fire Zone 106R is "tar and gravel" built-up roofing on a cncrete bas
's open to the atmosphere and contains th A
4.MM.3.1 Essential Eguipment within Fire Zone 106R See Appendix R Essential Equipment List, Reference 15.
9.6A-229 Rev. 17
4.MM.3.2 Fire zone 106R - combustible Loadings SOURCE QUANTITY (BTU)
.2a cable Insulation -- _-
.2b oils _ _
.2c others TOTAL Heat load (BTU/sq. ft.): Neglig gible 4.MM.3.3 Fire control
.4a Physical Containment:
Fire zone Boundary walls I ..
North: open I south: open East: open West: Open ceiling: open Floor: row
.4b Detection:
None
.4c Fire Protection Systems:
F'- .
- 1. Primar -
- 2. secondary -
.. .... . .i I...
, i ..
.4d smoke Venting: -
This fire zone is open to the atmosphere.
9.6A-230 90 Rev 8 7/! I
4.MM.4 APPENDIX R EXEMPTIONS Exemotion MM.1.
Exemption MM.'2 see section.3.11.2 .1 c) justification for Exemption The control Room is an area that is continuously manned in accordance with existing technical specifications. This assures that any fire occurring within the control Roo will be auicklv detcte n CL Inn In accordance with the requirements of 10 CFR Part 50 Appendix R sections III.L, alternate shutdown remote from the control Room will be provided.
The in situ combustibles in the Control Room consist of cables and components located within control boards, panels and control consoles and miscellaneous paper in the form of books, manuals and computer printouts.
A review of potential transient combustibles for this fire area was conducted by the Factory Mutual Research corporation for FPL.- The results of this review indicate that there are no expected transient combustibles for this fire area.
Fire protection features existing for this fire area are active and passive in nature. Passive fire protection is provided by the steel cabinets and control consoles which serve to contain in situ combustibles in discrete quantities and the spatial separation between consoles and cabinets.
Active fire protection is provided by the installed fire detection system which will provide early warning of any fire in this area allowing the operators to respond before significant development occurs, and by the continuous presence of operators in this area.
In conclusion, it is FPL'S position that the alternate shutdown system and the existing fire protection features combined with the continuous manning of this area provide a level of fire protection consistent with the fire hazards, both in situ and transient identified for this fire area and that these features provide assurance that at least one train of safe shutdown equipment and cables will be free of fire damage.
- 9. 6A-231 Rev. 15 4/98
- (I --
Exemption MM.3 Deleted Exemption MM.4 Deleted Exemption MM.5 FPL requested (Reference 38) and was granted (Reference 41) exemption from that portion of Appendix R to 10 CFR 50 section III.G.2.a which requires the enclosure of cables and equipment and associated non-safety circuits of one redundant train in a fire barrier having a 3-hour rating. specifically, exemption is requested to provide separation by a 25-minute rated fire barrier until a horizontal distance of 10' is attained.
Justification for Exemption This fire zone is an open, roof-top outdoor area, which prevents the stratification of hot ases or other products of c sqRb ft rng/
redundant cables should a fire occur. The roof is
- 7 construction with a built-up tar and gravel cover. e undant safe sh wn equipment are separated by a horizontal distance greater than 10'. circuit rotection for this area is provided by 25-minute rated fire barrier until a horizontal distance of 10' is attained. Intervening in situ combustible loading is negligible.
FIRE HAZARD ANALYSIS FOR FIRE AREA NN 4.NN DESCRIPTION OF FIRE AREA NN is the Uni DC Equipment Room, located on the levation of the 1_ The area is comprised of Fire ne A. Fire zone 1i8rwas subivi e as a result of Appendix R into Fire zones 108A and 108B by the installation of a two hour rated fire barrier.
_ This separation created Fire Area NN SFire Zone 108A) and Fire Area 00 (Fire zone 108B?. -Fire-Area 00 contains "B' train equipment and Fire Area NN contains 'A"-train equipment. Pertinent fire zone details are provided below.
Fire Area NN and the essential equipment and cables within have been evaluated with respect to protection and separation criteria of Appendix R Section III-G.2 to assure that the ability to safely shut down the plant is not adversely affected by a single fire event.
4.NN.1 FIRE ZONE 108A - UNIT 3 AND 4 A DC EQUIPMENT ROOM Fire zone 108A is bounded on the floor, ceiling and walls by a 3-hour rated fire barrier except for the dividing wall between Fire Zones 108A and 108B, which is a 2-hour rated fire barrier .and non-rated door D106-1. An.
=AA = .a 4.NN.1.1 Essential Eauipment within Fire Zone 108A see Appendix R Essential.Equipment List, Reference 15.
4.NN.1.2 Fire Zone 108A - combustible Loadings SOURCE QUANTIT (BTU)
- 9.64-232 09/10/2001