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| ==References:== | | ==References:== |
| : 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266) | | : 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266) |
| : 2. NRC E-mail "Request for Additional Information | | : 2. NRC E-mail "Request for Additional Information |
| -Turkey Point 3 & 4 -LAR-242 (CACs MF7557 & MF7558)," August 11, 2016 (ML16228A004) | | -Turkey Point 3 & 4 -LAR-242 (CACs MF7557 & MF7558)," August 11, 2016 (ML16228A004) |
| : 3. Florida Power & Light Company letter L-2016-172, "Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," September 1, 2016 (ML16260A399) | | : 3. Florida Power & Light Company letter L-2016-172, "Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," September 1, 2016 (ML16260A399) |
| : 4. NRC E-mail "Turkey Point 3 and 4 RAJ for LAR 242 Snubber TSs (CACs MF7557/58)" October 18, 2016 (ML16292A716) | | : 4. NRC E-mail "Turkey Point 3 and 4 RAJ for LAR 242 Snubber TSs (CACs MF7557/58)" October 18, 2016 (ML16292A716) |
| In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 242 for Turkey Point Units 3 and 4. The proposed' amendment would revise Technical Specification (TS) 3/4.7.6, Snubbers, to conform with the Snubber Testing Program. The Snubber Testing Program implements Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," of the ASME -oM Code, 2004 Edition with 2005 and 2006 Addenda. In Reference 2, the NRC staff requested additional information (RAJ) to complete its review of LAR 242. FPL provided a response to the Reference 2 RAJ in Reference | | In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 242 for Turkey Point Units 3 and 4. The proposed' amendment would revise Technical Specification (TS) 3/4.7.6, Snubbers, to conform with the Snubber Testing Program. The Snubber Testing Program implements Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," of the ASME -oM Code, 2004 Edition with 2005 and 2006 Addenda. In Reference 2, the NRC staff requested additional information (RAJ) to complete its review of LAR 242. FPL provided a response to the Reference 2 RAJ in Reference |
| : 3. In Reference 4, the NRC staffrequested additional information resulting from the original application and the Reference 3 RAJ response. | | : 3. In Reference 4, the NRC staffrequested additional information resulting from the original application and the Reference 3 RAJ response. |
| Enclosed is the FPL response to the Reference 4 / J 7 RAL . Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035 | | Enclosed is the FPL response to the Reference 4 / J 7 RAL . Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035 |
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| Proposed TS 6.8.4.m, Snubber Testing Program, specifies that the program includes the applicable provisions of ASME Section XI and OM codes. Attachment 3 of Reference 1 contains the Turkey Point Snubber Testing Program Plan (Plan). Sections 1.2 and 3.1 of the Plan specify that integral and nonintegral structural attachments for snubber assemblies shall be examined in accordance with the requirements of the ASME B&PV Code Section XI, Article IWF-2500(a), (b), (c) and (d). Although the Code edition is not specified in the Plan, ASME Section XI 2007 Edition with 2008 Addenda is being used from Florida Power & Light Company Enclosure L-2016-204 Page 3of3 pin-to-structure and pin-to-piping (associated attachment hardware) inspections (References 2, 3 and 4). As stated in Section 1.1 of the Plan, ASME OM Code 2004 Edition with 2005 and 2006 Addenda is being used for snubber inspection and testing from pin-to-pin inclusively. | | Proposed TS 6.8.4.m, Snubber Testing Program, specifies that the program includes the applicable provisions of ASME Section XI and OM codes. Attachment 3 of Reference 1 contains the Turkey Point Snubber Testing Program Plan (Plan). Sections 1.2 and 3.1 of the Plan specify that integral and nonintegral structural attachments for snubber assemblies shall be examined in accordance with the requirements of the ASME B&PV Code Section XI, Article IWF-2500(a), (b), (c) and (d). Although the Code edition is not specified in the Plan, ASME Section XI 2007 Edition with 2008 Addenda is being used from Florida Power & Light Company Enclosure L-2016-204 Page 3of3 pin-to-structure and pin-to-piping (associated attachment hardware) inspections (References 2, 3 and 4). As stated in Section 1.1 of the Plan, ASME OM Code 2004 Edition with 2005 and 2006 Addenda is being used for snubber inspection and testing from pin-to-pin inclusively. |
| FPL is in agreement that reference to TS 4.0.5 is no longer needed and can be deleted because proposed TS 6.8.4.m, Snubber Testing Program, includes the ASME Section XI requirements for snubber attachment inspection. | | FPL is in agreement that reference to TS 4.0.5 is no longer needed and can be deleted because proposed TS 6.8.4.m, Snubber Testing Program, includes the ASME Section XI requirements for snubber attachment inspection. |
| A revised TS page 3/4 7-22 is attached indicating the proposed change to delete the reference to TS 4.0.5. References | | A revised TS page 3/4 7-22 is attached indicating the proposed change to delete the reference to TS 4.0.5. References |
| : 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266) . 2. Florida Power & Light Company letter L-2015-101, "Fifth Ten-Year Inservice Inspection (ISI) Interval Relief Request No. 3," June 8, 2015 (ML15181A251) | | : 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266) . 2. Florida Power & Light Company letter L-2015-101, "Fifth Ten-Year Inservice Inspection (ISI) Interval Relief Request No. 3," June 8, 2015 (ML15181A251) |
| : 3. Florida Power & Light Company letter L-2015-284, "Inservice Inspection Program, Fifth Ten Year Interval, Response to Request for Additional Information for Relief Request No. 3," December 4, 2015 (ML15351A405) | | : 3. Florida Power & Light Company letter L-2015-284, "Inservice Inspection Program, Fifth Ten Year Interval, Response to Request for Additional Information for Relief Request No. 3," December 4, 2015 (ML15351A405) |
| : 4. NRC Letter, "Turkey Point Nuclear Generating Unit Nos. 3 and 4 -Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval -Alternative for | | : 4. NRC Letter, "Turkey Point Nuclear Generating Unit Nos. 3 and 4 -Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval -Alternative for |
| * Examination of Snubbers (CAC Nos. MF6386 and MF6387), March 9, 2016 (ML16047Al | | * Examination of Snubbers (CAC Nos. MF6386 and MF6387), March 9, 2016 (ML16047Al |
| : 18) Attachment Revised Markup of Technical Specifications page 3/4 7-22 Florida Power & Light Company ATTACHMENT Revised Markup of the Technical Specifications (I page follows) L-2016-204 Attachment PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE. T he only snubbers excluded from the requ i rements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system. APPLICABILITY | | : 18) Attachment Revised Markup of Technical Specifications page 3/4 7-22 Florida Power & Light Company ATTACHMENT Revised Markup of the Technical Specifications (I page follows) L-2016-204 Attachment PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE. T he only snubbers excluded from the requ i rements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system. APPLICABILITY |
| : MODES 1 , 2 , 3 , and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES. ACTION: determine the impact With one or more snubbers inoperabl n any system , within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.6.f on the attached componen or declare the attached system inoperable and follow the appropriate ACTION statement for that system. by evaluation in accordance with Specification 4.7.6, Snubber Testing S RVEILLANCE RE UIREMENT As used in this specification , type of snubber shall mean snubbers of the same design and manufacturer , irrespective of capacity. | | : MODES 1 , 2 , 3 , and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES. ACTION: determine the impact With one or more snubbers inoperabl n any system , within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.6.f on the attached componen or declare the attached system inoperable and follow the appropriate ACTION statement for that system. by evaluation in accordance with Specification 4.7.6, Snubber Testing S RVEILLANCE RE UIREMENT As used in this specification , type of snubber shall mean snubbers of the same design and manufacturer , irrespective of capacity. |
| &.-Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4 .7 2. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4 .7 2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 151and146. &. Visual Inspection Acceptance Criteria Visual inspections shall *1erify that: (1) the snubber has no visible indications of damage or impaired OPERABILITY , (2) attachments to the foundation or supporting structure are secure , and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure. Snubbers which appear inoperable as a result of visual TURKEY POINT -UNITS 3 & 4 3/4 7-22 AMENDMENT I}} | | &.-Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4 .7 2. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4 .7 2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 151and146. &. Visual Inspection Acceptance Criteria Visual inspections shall *1erify that: (1) the snubber has no visible indications of damage or impaired OPERABILITY , (2) attachments to the foundation or supporting structure are secure , and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure. Snubbers which appear inoperable as a result of visual TURKEY POINT -UNITS 3 & 4 3/4 7-22 AMENDMENT I}} |
Letter Sequence Response to RAI |
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CAC:MF7557, TS Inservice Testing (IST) Program Removal (Approved, Closed) |
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MONTHYEARML16125A0142016-05-0303 May 2016 NRR E-mail Capture - NRC LIC-109 Acceptance Review Results for Turkey Point 3 & 4 License Amendment Request No. 242 Project stage: Acceptance Review ML16228A0042016-08-11011 August 2016 NRR E-mail Capture - Request for Additional Information - Turkey Point 3 & 4 - LAR-242 (CACs MF7557 & MF7558) Project stage: RAI L-2016-172, Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval2016-09-0101 September 2016 Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval Project stage: Response to RAI ML16292A7162016-10-18018 October 2016 NRR E-mail Capture - Turkey Point 3 and 4 RAI for LAR 242 Snubber TSs (CACs MF7557/58) Project stage: RAI L-2016-204, Response to Request for Additional Information 7 Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval2016-11-10010 November 2016 Response to Request for Additional Information 7 Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval Project stage: Response to RAI L-2016-221, License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Inter-Val, Supplement2016-12-0202 December 2016 License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Inter-Val, Supplement Project stage: Supplement ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers Project stage: Approval 2016-05-03
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Category:Letter type:L
MONTHYEARL-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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule 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-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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-2023-114, 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-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. 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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update 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-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 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-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums 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-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study 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-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 ML23151A4372023-05-24024 May 2023 Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database ML23095A0082023-04-0404 April 2023 Attachment 2 - Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-051, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information2022-03-29029 March 2022 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information L-2021-213, Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology2021-11-19019 November 2021 Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology L-2021-207, Response to Request for Additional Information for ISI Relief Request No. 102021-10-25025 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 L-2021-197, Response to Request for Additional Information for ISI Relief Request No. 102021-10-15015 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 ML21258A3792021-09-14014 September 2021 Response to Request for Additional Information, Relief Requests 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Extension of Inspection Interval for Turkey Point Unit 3 and Unit 4 Reactor. L-2020-111, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report2020-06-24024 June 2020 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report L-2020-081, Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor2020-06-0808 June 2020 Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor L-2020-083, Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re2020-05-21021 May 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re L-2020-071, Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2020-04-16016 April 2020 Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2020-064, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information2020-04-0909 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 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-2019-135, Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-07-22022 July 2019 Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications ML19158A5032019-06-0707 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Turkey Point ESA Section 7 Consultation L-2019-114, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response2019-06-0404 June 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 82019-03-15015 March 2019 Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8 L-2019-037, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses2019-03-0606 March 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses2019-03-0101 March 2019 Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses ML19056A1252019-02-25025 February 2019 Turky Point SLRA RAIs 1 2 3 4 5 6 7 8 9 11 - Set 8 Rev 1 Irradiated Concrete-Steel Responses L-2019-012, Response to Follow-on NRC RAI No. B.2.3.9-1 a2019-02-13013 February 2019 Response to Follow-on NRC RAI No. B.2.3.9-1 a L-2019-023, Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals2019-01-31031 January 2019 Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals L-2018-234, Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision2018-12-21021 December 2018 Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision L-2018-223, Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses2018-12-14014 December 2018 Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses L-2018-222, Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses2018-12-12012 December 2018 Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses L-2018-218, Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review2018-11-28028 November 2018 Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review2018-11-28028 November 2018 Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review2018-11-0202 November 2018 Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review L-2018-166, WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings.2018-10-31031 October 2018 WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings. ML18299A1142018-10-24024 October 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 4 Responses L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items ML18296A0242018-10-16016 October 2018 Set 3 Response to Request for Additional Information to Subsequent License Renewal Application Safety Review 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 ML18299A1172018-10-12012 October 2018 Framatome Calculation No. 32-9280712, Rev. 002, Tp CRDM Lower Joint Environmentally Assisted Fatigue Dated October 12, 2018 (Non-Proprietary) 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 ML18283A3102018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application Environmental Review 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-2018-154, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses2018-09-14014 September 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses 2023-08-07
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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.90 L-2016-204 November 10, 2016 Response to Request for Additional Information 7 Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval
References:
- 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266)
- 2. NRC E-mail "Request for Additional Information
-Turkey Point 3 & 4 -LAR-242 (CACs MF7557 & MF7558)," August 11, 2016 (ML16228A004)
- 3. Florida Power & Light Company letter L-2016-172, "Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," September 1, 2016 (ML16260A399)
- 4. NRC E-mail "Turkey Point 3 and 4 RAJ for LAR 242 Snubber TSs (CACs MF7557/58)" October 18, 2016 (ML16292A716)
In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 242 for Turkey Point Units 3 and 4. The proposed' amendment would revise Technical Specification (TS) 3/4.7.6, Snubbers, to conform with the Snubber Testing Program. The Snubber Testing Program implements Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," of the ASME -oM Code, 2004 Edition with 2005 and 2006 Addenda. In Reference 2, the NRC staff requested additional information (RAJ) to complete its review of LAR 242. FPL provided a response to the Reference 2 RAJ in Reference
- 3. In Reference 4, the NRC staffrequested additional information resulting from the original application and the Reference 3 RAJ response.
Enclosed is the FPL response to the Reference 4 / J 7 RAL . Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035
. Florida Power & Light Company L-2016-204 Page2 of2 The attachment to the enclosure provides a revised mark-up of TS Surveillance Requirement 4.7.6 on TS page 3/4 7-22 showing a revision to the proposed changes consistent with the Reference 4 RAI. The mark-up supersedes the corresponding mark-up provided in References 1 and3. This does not alter the conclusion in Reference 1 that the changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with No new or revised commitments are included in this letter. Should you have any questions regarding this submission, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698. , I declare under. penalty of perjury that the foregoing is true and correct. Executed on November 1o , 2016. . ...... <.:tw Thomas Summers "5 Site Vfoe President Turkey Point Nuclear Plant Enclosure cc: NRC Regional Administrator, Region II NRC Senior Resident Inspector NRC Project Manager Ms. Cindy Becker, Florida Department of Health Florida Power & Light Company Enclosure ENCLOSURE Response to Request for Additional Information 7 License Amendment Request 242 Changes to Snubber Surveillance Requirements Snubber Testing Program Plan -Fifth Inspection Interval L-2016-204 Page 1of3 Florida Power & Light Company Enclosure RAI7 L-2016-204 Page 2 of3 In its application dated April 4, 2016, the licensee requested, in part, the following changes to Surveillance Requirement (SR) 4.7.6: 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection Snubber TestingProgram in Specification 6.8.4.m in addition to the requirements of Specification 4.0.5. In its RAI dated August 11, 2016, the NRC requested (via RAI 3) the licensee to clarify the use of TS 4.0.5 along with newly added TS 6.8.4.m and to confirm whether these TSs are duplicative and/or if TS 6.8.4.m encompasses all requirements of TS 4.0.5. In its letter dated September 1, 2016, the licensee responded to RAI 3 stating that TS 6.8.4.m and TS 4.0.5 are duplicative with respect to snubbers and that the licensee has proposed to delete reference to TS 4.0.5 in TS 4.7.6 via a separate license amendment application.
In Attachment 3 to its application dated April 4, 2016, the licensee provided the Turkey Point Nuclear Plant Unit 3 and 4 Snubber Testing Program Plan, which is based on the ASME OM Code 2004 Edition with 2005 and 2006 Addenda. In TS 4.0.5, the ASME OM Code is only used for inservice testing of pumps and valves; it is not applicable to snubbers.
Therefore, TS 6.8.4.m and TS 4.0.5 do not appear to be duplicative with respect to snubbers, and the "in addition to the requirements of Specification 4.0.5" no longer appears to be applicable to this SR. The staff requests the licensee to revise the application by proposing to delete "in addition to the requirements of Specification 4.0.5," or to provide additional justification for retaining this phrasing in Specification 4.7.6. FPL Response The FPL response to RAI 3 stated: "TS 6.8.4.m and TS 4.0.5 are duplicative with respect to snubbers." The response is clarified herewith insofar as the duplication of requirements for snubber testing is only for the inservice inspection (ISI) of ASME Code Class 1, 2, and 3 components in accordance with Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code and applicable Addenda as required by 10 CFR 50, Section 50.55a. As stated in RAI 7 above, the inservice testing (IST) provisions of Technical Specification (TS) 4.0.5 pertain only to pumps and valves; however, the ISI provisions apply to ASME Code Class 1, 2 and 3 components which include snubber attachments.
Proposed TS 6.8.4.m, Snubber Testing Program, specifies that the program includes the applicable provisions of ASME Section XI and OM codes. Attachment 3 of Reference 1 contains the Turkey Point Snubber Testing Program Plan (Plan). Sections 1.2 and 3.1 of the Plan specify that integral and nonintegral structural attachments for snubber assemblies shall be examined in accordance with the requirements of the ASME B&PV Code Section XI, Article IWF-2500(a), (b), (c) and (d). Although the Code edition is not specified in the Plan, ASME Section XI 2007 Edition with 2008 Addenda is being used from Florida Power & Light Company Enclosure L-2016-204 Page 3of3 pin-to-structure and pin-to-piping (associated attachment hardware) inspections (References 2, 3 and 4). As stated in Section 1.1 of the Plan, ASME OM Code 2004 Edition with 2005 and 2006 Addenda is being used for snubber inspection and testing from pin-to-pin inclusively.
FPL is in agreement that reference to TS 4.0.5 is no longer needed and can be deleted because proposed TS 6.8.4.m, Snubber Testing Program, includes the ASME Section XI requirements for snubber attachment inspection.
A revised TS page 3/4 7-22 is attached indicating the proposed change to delete the reference to TS 4.0.5. References
- 1. Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan -Fifth Inspection Interval," April 4, 2016 (ML16110A266) . 2. Florida Power & Light Company letter L-2015-101, "Fifth Ten-Year Inservice Inspection (ISI) Interval Relief Request No. 3," June 8, 2015 (ML15181A251)
- 3. Florida Power & Light Company letter L-2015-284, "Inservice Inspection Program, Fifth Ten Year Interval, Response to Request for Additional Information for Relief Request No. 3," December 4, 2015 (ML15351A405)
- 4. NRC Letter, "Turkey Point Nuclear Generating Unit Nos. 3 and 4 -Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval -Alternative for
- 18) Attachment Revised Markup of Technical Specifications page 3/4 7-22 Florida Power & Light Company ATTACHMENT Revised Markup of the Technical Specifications (I page follows) L-2016-204 Attachment PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE. T he only snubbers excluded from the requ i rements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system. APPLICABILITY
- MODES 1 , 2 , 3 , and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES. ACTION: determine the impact With one or more snubbers inoperabl n any system , within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.6.f on the attached componen or declare the attached system inoperable and follow the appropriate ACTION statement for that system. by evaluation in accordance with Specification 4.7.6, Snubber Testing S RVEILLANCE RE UIREMENT As used in this specification , type of snubber shall mean snubbers of the same design and manufacturer , irrespective of capacity.
&.-Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4 .7 2. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4 .7 2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 151and146. &. Visual Inspection Acceptance Criteria Visual inspections shall *1erify that: (1) the snubber has no visible indications of damage or impaired OPERABILITY , (2) attachments to the foundation or supporting structure are secure , and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure. Snubbers which appear inoperable as a result of visual TURKEY POINT -UNITS 3 & 4 3/4 7-22 AMENDMENT I