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| {{#Wiki_filter:October 19, 2017 L-2017-188 10 CFR 50.90 | | {{#Wiki_filter:October 19, 2017 L-2017-188 10 CFR 50.90 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 Renewed Facility Operating Licenses DPR-31 and DPR-41 Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents |
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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 Renewed Facility Operating Licenses DPR | |
| -31 and DPR | |
| -41 Supplemental Information for License Amendment Request 2 55 , Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents | |
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| ==References:== | | ==References:== |
| | : 1) FPL letter L-2017-110 dated August 23, 2017, License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents (Accession No. ML17235B008) |
| | : 2) NRC letter dated October 6, 2017, Turkey Point Nuclear Generating Unit Nos. 3 and 4 - |
| | Supplemental Information Needed for Acceptance of License Amendment Request 255 for the Relocation of the Requirements for Explosive Gas Monitoring, Gas Decay Tanks and Standby Steam Generator Feed Pumps (CAC NOS. MG0143 and MG0144) |
| | In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 255 for Turkey Point Nuclear Plant Units 3 and 4 (Turkey Point), Renewed Facility Operating Licenses DPR-31 and DPR-41, respectively. The proposed license amendments modify the Turkey Point Technical Specifications by relocating the Explosive Gas Monitoring Instrumentation, Explosive Gas Mixture, and Gas Decay Tanks System requirements to licensee controlled documents and establishing a Gas Decay Tank Explosive Gas and Radioactivity Monitoring Program. The license amendments additionally relocate the Standby Feedwater System requirements to licensee controlled documents and modify related Auxiliary Feedwater System requirements. |
| | In Reference 2, the NRC staff requested supplemental information deemed necessary to complete its acceptance review of LAR 255. |
| | The enclosure to this letter provides FPLs response to the supplemental information request. |
| | Florida Power & Light Company 9760 SW 344 St., Homestead, FL 33035 |
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| 1)FPL letter L
| | Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Page 2of2 This letter contains no new or revised regulatory commitments. This supplemental information does not alter the conclusion in Reference 1 that the proposed changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the proposed changes. |
| -2017-110 dated August 2 3, 201 7 , License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents (Accession No. ML17235B008) 2)NRC letter dated October 6 , 201 7 , Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Supplemental Information Needed for Acceptance of License Amendment Request 255 for the Relocation of the Requirements for Explosive Gas Monitoring, Gas Decay Tanks and Standby Steam Generator Feed Pumps (CAC NOS. MG0143 and MG0144)
| | Should you have any questions regarding this submission, please contact Mr. Mitch Guth, Turkey Point Licensing Manager, at 305-246-6698. |
| In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 255 for Turkey Point Nuclear Plant Units 3 and 4 (Turkey Point), Renewed Facility Operating Licenses DPR-31 and DPR-41, respectively. The proposed license amendment s modify the Turkey Point Technical Specifications by relocating the Explosive Gas Monitoring Instrumentation, Explosive Gas Mixture, and Gas Decay Tanks System requirements to licensee controlled documents and establishing a Gas Decay Tank Explosive Gas and Radioactivity Monitoring Program. The license amendments additionally relocate the Standby Feedwater System requirements to licensee controlled documents and modify related Auxiliary Feedwater System requirements.
| | I declare under penalty of perjury that the foregoing is true and correct. |
| In Reference 2, the NRC staff requested supplemental information deemed necessary to complete its acceptance review of LAR 2 55.
| | Executed on October 19, 2017 Sincerely, Thomas Summers Regional Vice President - Southern Region Florida Power & Light Company |
| The enclosure to this letter provides FPL's response to the supplemental information request.
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| Florida Power & Light Company 9760 SW 344 St., Homestead, FL 33035 Turkey Point Nuclear Plant Docket Nos. 50-250 and 50-251 L-2017-188 Page 2of2 This letter contains no new or revised regulatory commitments.
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| This supplemental information does not alter the conclusion in Reference 1 that the proposed changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the proposed changes. Should you have any questions regarding this submission, please contact Mr. Mitch Guth, Turkey Point Licensing Manager, at 305-246-6698. | |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on October 19, 2017 Sincerely, Thomas Summers Regional Vice President | |
| -Southern Region Florida Power & Light Company | |
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| ==Enclosure:== | | ==Enclosure:== |
| | Response to Supplemental Information Request cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health |
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| Response to Supplemental Information Request cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50
| | Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 1 of 4 Enclosure Turkey Point Units 3 and 4 Response to Supplemental Information Request for License Amendment Request 255 Relocate Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Document |
| -250 and 50 | |
| -251 Enclosure Page 1 of 4 Enclosure Turkey Point Units 3 and 4 Response to Supplemental Information Request for License Amendment Request 255 Relocate Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Document | |
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| Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50 | | Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 2 of 4 NRC comment: |
| -250 and 50 | | Provide the basis for concluding the Standby Feedwater System is not significant to public health and safety. The basis should include an assessment of operating experience and risk insights and a discussion of the safety significance of the functions . |
| -251 Enclosure Page 2 of 4 NRC comment: Provide the basis for concluding the Standby Feedwater System is not significant to public health and safety. The basis should include an assessment of operating experience and risk insights and a discussion of the safety significance of the functions- . | |
| FPL Response: | | FPL Response: |
| The proposed license amendments relocate the requirements of Technical Specification (TS) 3.7.1.6, Standby Feedwater System, to licensee controlled documents. The proposed amendments also delete the special reporting requirements of TS 3.7.1.6 such that no notification to the NRC would occur in the event a Standby Steam Generator Feedwater Pump (SSGFP) or the Demineralized Water Storage Tank (DWST) is non-operational in excess of the current TS 3.7.1.6 specified periods triggering special reporting. | | The proposed license amendments relocate the requirements of Technical Specification (TS) 3.7.1.6, Standby Feedwater System, to licensee controlled documents. The proposed amendments also delete the special reporting requirements of TS 3.7.1.6 such that no notification to the NRC would occur in the event a Standby Steam Generator Feedwater Pump (SSGFP) or the Demineralized Water Storage Tank (DWST) is non-operational in excess of the current TS 3.7.1.6 specified periods triggering special reporting. |
| In proposing LAR 255, FPL evaluated the Standby Feedwater System's safety-significance and concluded that it does not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS Limiting Condition for Operation (LCO). Consistent with Criterion 4 of 10 CFR 50.36(c)(2)(ii), the evaluation included a determination of whether operating experience or probabilistic risk assessment have shown the Standby Feedwater System's structures, systems and components (SSCs) to be significant to public health and safety. | | In proposing LAR 255, FPL evaluated the Standby Feedwater Systems safety-significance and concluded that it does not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS Limiting Condition for Operation (LCO). Consistent with Criterion 4 of 10 CFR 50.36(c)(2)(ii), the evaluation included a determination of whether operating experience or probabilistic risk assessment have shown the Standby Feedwater Systems structures, systems and components (SSCs) to be significant to public health and safety. |
| | Regarding the Standby Feedwater Systems risk significance: |
| | * For internal events and flooding events, a sensitivity analysis was done by increasing the failure probability of the SSGFPs by two orders of magnitude. This results in the systems contribution to Turkey Points core damage frequency (CDF) remaining below 1E-6 per year. A substantial portion of the systems risk significance comes from the Turkey Point Fire PRA due to certain fire scenarios that credit the SSGFPs. |
| | However, it has long been the NRCs position that fire scenarios and protective features are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion in the TS as an LCO. |
| | Regarding current Standby Feedwater System monitoring: |
| | * The Turkey Point NFPA 805 Monitoring Program identifies the SSGFPs as high safety significance (HSS) for certain fire scenarios and thereby subject to NFPA 805 program monitoring. Under this program, target unreliability and unavailability criteria are established based on Fire PRA failure probabilities. The NFPA 805 Monitoring Program screening determination concluded that the current Maintenance Rule (MR) Program monitoring of the SSGFPs is acceptable and that additional NFPA 805 Monitoring Program inspections and tests are not warranted (Reference 1). |
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| Regarding the Standby Feedwater System's risk significance: | | Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 3 of 4 |
| For internal events and flooding events, a sensitivity analysis was done by increasing the failure probability of the SSGFPs by two orders of magnitude. This results in the system's contribution to Turkey Point's core damage frequency (CDF) remaining below 1E-6 per year. A substantial portion of the system's risk significance comes from the Turkey Point Fire PRA due to certain fire scenarios that credit the SSGFPs. However, it has long been the NRC's position that fire scenarios and protective features are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion in the TS as an LCO.
| | * The Turkey Point MR Program established reliability performance criteria for both SSGFPs and adds unavailability criteria for the diesel-driven SSGFP. |
| | Regarding operating experience (OE): |
| | * FPL conducted a search for OE related to similar standby feedwater systems. |
| | NUREG/CR-5764, Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station (Reference 2), was identified as a document describing some level of OE. The report details a listing of the risk important AFW components at the Ginna Nuclear Power Station based upon PRA, industry operating experience, etc., and the various failure causes. Though many standby AFW system components were identified as risk significant, none were explicitly identified as affecting the operational performance and readiness of the AFW system and moreover, none were explicitly attributed to the AFW systems failure history. |
| | While the AFW system at the Ginna Nuclear Power Station is similar in design to the one at Turkey Point, the standby AFW system at Ginna was retrofitted to address a high energy line break (HELB) outside Containment event and thereby satisfies the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The system is supported by a safety-related ventilation system and powered by redundant Class lE electrical systems. In contrast, Turkey Points Standby Feedwater system is a non-safety grade system used for plant startup and shutdowns and is located in the outside environs. |
| | Consequently, the OE included in the report was not deemed directly applicable. |
| | The system is not relied upon to mitigate a HELB or any other postulated transient or accident, and though credited in select fire scenarios, its function as a backup to the AFW system in these scenarios is not subject to the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a LCO. |
| | * The NRCs final policy statement on TS improvements (Reference 3) states that the Residual Heat Removal (RHR) system is one example of a system satisfying Criterion 4 of 10 CFR 50.36(c)(2)(ii) and thereby subject to inclusion as a TS LCO. In Standard Technical Specification (STS) 3.9.5 of NUREG-1431, Volume 2, Bases (Reference 4), the only description of the RHR system satisfying Criterion 4 is in MODE 6 with the reactor cavity water level 23 feet or more above the reactor vessel flange. The guidance explains that only one RHR train is required in this configuration because the water above the reactor vessel flange provides backup capability for decay heat removal. In essence, the single RHR train is credited as the primary means and the cavity water level as the backup means for maintaining fuel cladding integrity during this operational mode. |
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| Regarding current Standby Feedwater System monitoring:
| | Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 4 of 4 In contrast, the highly reliable AFW trains are credited as the primary and backup means for decay heat removal capability during MODES 1, 2 and 3. In the event one AFW train is unavailable, the redundant AFW train is capable of performing its specified function. The non-safety grade Standby Feedwater System provides a shutdown function but not a safety-related or emergency function. Only for fires disabling all three AFW pumps is credit taken for the Standby Feedwater System. As stated earlier, fire scenarios are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The FPP is not addressed in the TS other than to establish administrative controls consistent with other programs implemented by license condition. |
| The Turkey Point NFPA 805 Monitoring Program identifies the SSGFPs as high safety significance (HSS) for certain fire scenarios and thereby subject to NFPA 805 program monitoring. Under this program, t arget unreliability and unavailability criteria are established base d on Fire PRA failure probabilities. The NFPA 805 Monitoring Program screening determination concluded that the current Maintenance Rule (MR) Program monitoring of the SSGFPs is acceptable and that additional NFPA 805 Monitoring Program inspections and tests are not warranted (Reference 1).
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| Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50
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| -250 and 50
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| -251 Enclosure Page 3 of 4 The Turkey Point MR Program established reliability performance criteria for both SSGFPs and adds unavailability criteria for the diesel-driven SSGFP.
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| Regarding operating experience (OE): FPL conducted a search for OE related to similar standby feedwater systems. NUREG/CR-5764, "Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station" (Reference 2), was identified as a document describing some level of OE. The report details a listing of the risk important AFW components at the Ginna Nuclear Power Station based upon PRA, industry operating experience, etc., and the various failure causes. Though many standby AFW system components were identified as risk significant, none were explicitly identified as affecting the operational performance and readiness of the AFW system and moreover, none were explicitly attributed to the AFW system's failure history.
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| While the AFW system at the Ginna Nuclear Power Station is similar in design to the one at Turkey Point, the standby AFW system at Ginna w as retrofitted to address a high energy line break (HELB) outside Containment event and thereby satisfies the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The system is supported by a safety
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| -related ventilation system and powered by redundant Class lE electrical systems. In contrast, Turkey Point's Standby Feedwater system is a non-safety grade system used for plant startup and shutdowns and is located in the outside environs. Consequently, the OE included in the report was not deemed directly applicable. The system is not relied upon to mitigate a HELB or any other postulated transient or accident, and though credited in select fire scenarios, its function as a backup to the AFW system in these scenarios is not subject to the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a LCO.
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| The NRC's final policy statement on TS improvements (Reference
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| : 3) states that the Residual Heat Removal (RHR) system is one example of a system satisfying Criterion 4 of 10 CFR 50.36(c)(2)(ii) and thereby subject to inclusion as a TS LCO. In Standard Technical Specification (STS) 3.9.5 of NUREG
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| -1431, Volume 2, Bases (Reference 4), the only description of the RHR system satisfying Criterion 4 is in MODE 6 with the reactor cavity water level 23 feet or more above the reactor vessel flange. The guidance explains that only one RHR train is required in this configuration because the water above the reactor vessel flange provides backup capability for decay heat removal. In essence, the single RHR train is credited as the primary means and the cavity water level as the backup means for maintaining fuel cladding integrity during this operational mode.
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| Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50 | |
| -250 and 50 | |
| -251 Enclosure Page 4 of 4 In contrast, the highly reliable AFW trains are credited as the primary and backup means for decay heat removal capability during MODES 1, 2 and 3. In the event one AFW train is unavailable, the redundant AFW train is capable of performing its specified function. The non-safety grade Standby Feedwater System provides a shutdown function but not a safety-related or emergency function. Only for fires disabling all three AFW pumps is credit taken for the Standby Feedwater System. As stated earlier, fire scenarios are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The FPP is not addressed in the TS other than to establish administrative controls consistent with other programs implemented by license condition. | |
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| ==References:== | | ==References:== |
| | | : 1. Jensen Hughes Report #: 033006-RPT-002, PTN NFPA 805 Implementation - Task 2 Monitoring - NFPA 805 Monitoring Program Phase 2/3: Screening and Risk Target Values, Revision 3, October 24, 2016 |
| 1.Jensen Hughes Report #: 033006-RPT-002, PTN NFPA 805 Implementation - T ask 2 Mon itoring - NFPA 805 Monitoring Program Phase 2/3: Screening and Risk Target Values, Revision 3, October 24, 2016 2.NUREG/CR-5764, Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station, September 1991. | | : 2. NUREG/CR-5764, Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station, September 1991. |
| 3.NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132) 4.NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0, Volume 2 Bases (Accession No. ML12100A22 8)}} | | : 3. NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132) |
| | : 4. NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0, Volume 2 Bases (Accession No. ML12100A228)}} |
Letter Sequence Supplement |
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MONTHYEARL-2017-110, License Amendment Request 255, Relocate Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents2017-08-23023 August 2017 License Amendment Request 255, Relocate Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents Project stage: Request L-2017-188, Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents2017-10-19019 October 2017 Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents Project stage: Supplement L-2017-213, License Amendment Request 256, One-Time Extension of 3A Containment Spray (CS) Pump Completion Time2017-12-18018 December 2017 License Amendment Request 256, One-Time Extension of 3A Containment Spray (CS) Pump Completion Time Project stage: Request ML18047A0362018-02-0505 February 2018 NRR E-mail Capture - Draft Request for Additional Information - Turkey Point 3 and 4 LAR 255 (CAC Nos MG0143 and MG0144; EPID L-2017-LLA-0272) Project stage: Draft RAI ML18047A0352018-02-15015 February 2018 NRR E-mail Capture - Request for Additional Information - Turkey Point 3 and 4 LAR 255 (CAC Nos MG0143 and MG0144; EPID L-2017-LLA-0272) Project stage: RAI L-2018-075, Response to Request for Additional Information Regarding License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications ...2018-03-27027 March 2018 Response to Request for Additional Information Regarding License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications ... Project stage: Response to RAI 2017-08-23
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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
[Table view] |
Text
October 19, 2017 L-2017-188 10 CFR 50.90 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 Renewed Facility Operating Licenses DPR-31 and DPR-41 Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents
References:
- 1) FPL letter L-2017-110 dated August 23, 2017, License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents (Accession No. ML17235B008)
- 2) NRC letter dated October 6, 2017, Turkey Point Nuclear Generating Unit Nos. 3 and 4 -
Supplemental Information Needed for Acceptance of License Amendment Request 255 for the Relocation of the Requirements for Explosive Gas Monitoring, Gas Decay Tanks and Standby Steam Generator Feed Pumps (CAC NOS. MG0143 and MG0144)
In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 255 for Turkey Point Nuclear Plant Units 3 and 4 (Turkey Point), Renewed Facility Operating Licenses DPR-31 and DPR-41, respectively. The proposed license amendments modify the Turkey Point Technical Specifications by relocating the Explosive Gas Monitoring Instrumentation, Explosive Gas Mixture, and Gas Decay Tanks System requirements to licensee controlled documents and establishing a Gas Decay Tank Explosive Gas and Radioactivity Monitoring Program. The license amendments additionally relocate the Standby Feedwater System requirements to licensee controlled documents and modify related Auxiliary Feedwater System requirements.
In Reference 2, the NRC staff requested supplemental information deemed necessary to complete its acceptance review of LAR 255.
The enclosure to this letter provides FPLs response to the supplemental information request.
Florida Power & Light Company 9760 SW 344 St., Homestead, FL 33035
Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Page 2of2 This letter contains no new or revised regulatory commitments. This supplemental information does not alter the conclusion in Reference 1 that the proposed changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the proposed changes.
Should you have any questions regarding this submission, please contact Mr. Mitch Guth, Turkey Point Licensing Manager, at 305-246-6698.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on October 19, 2017 Sincerely, Thomas Summers Regional Vice President - Southern Region Florida Power & Light Company
Enclosure:
Response to Supplemental Information Request cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health
Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 1 of 4 Enclosure Turkey Point Units 3 and 4 Response to Supplemental Information Request for License Amendment Request 255 Relocate Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Document
Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 2 of 4 NRC comment:
Provide the basis for concluding the Standby Feedwater System is not significant to public health and safety. The basis should include an assessment of operating experience and risk insights and a discussion of the safety significance of the functions .
FPL Response:
The proposed license amendments relocate the requirements of Technical Specification (TS) 3.7.1.6, Standby Feedwater System, to licensee controlled documents. The proposed amendments also delete the special reporting requirements of TS 3.7.1.6 such that no notification to the NRC would occur in the event a Standby Steam Generator Feedwater Pump (SSGFP) or the Demineralized Water Storage Tank (DWST) is non-operational in excess of the current TS 3.7.1.6 specified periods triggering special reporting.
In proposing LAR 255, FPL evaluated the Standby Feedwater Systems safety-significance and concluded that it does not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS Limiting Condition for Operation (LCO). Consistent with Criterion 4 of 10 CFR 50.36(c)(2)(ii), the evaluation included a determination of whether operating experience or probabilistic risk assessment have shown the Standby Feedwater Systems structures, systems and components (SSCs) to be significant to public health and safety.
Regarding the Standby Feedwater Systems risk significance:
- For internal events and flooding events, a sensitivity analysis was done by increasing the failure probability of the SSGFPs by two orders of magnitude. This results in the systems contribution to Turkey Points core damage frequency (CDF) remaining below 1E-6 per year. A substantial portion of the systems risk significance comes from the Turkey Point Fire PRA due to certain fire scenarios that credit the SSGFPs.
However, it has long been the NRCs position that fire scenarios and protective features are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion in the TS as an LCO.
Regarding current Standby Feedwater System monitoring:
- The Turkey Point NFPA 805 Monitoring Program identifies the SSGFPs as high safety significance (HSS) for certain fire scenarios and thereby subject to NFPA 805 program monitoring. Under this program, target unreliability and unavailability criteria are established based on Fire PRA failure probabilities. The NFPA 805 Monitoring Program screening determination concluded that the current Maintenance Rule (MR) Program monitoring of the SSGFPs is acceptable and that additional NFPA 805 Monitoring Program inspections and tests are not warranted (Reference 1).
Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 3 of 4
- The Turkey Point MR Program established reliability performance criteria for both SSGFPs and adds unavailability criteria for the diesel-driven SSGFP.
Regarding operating experience (OE):
- FPL conducted a search for OE related to similar standby feedwater systems.
NUREG/CR-5764, Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station (Reference 2), was identified as a document describing some level of OE. The report details a listing of the risk important AFW components at the Ginna Nuclear Power Station based upon PRA, industry operating experience, etc., and the various failure causes. Though many standby AFW system components were identified as risk significant, none were explicitly identified as affecting the operational performance and readiness of the AFW system and moreover, none were explicitly attributed to the AFW systems failure history.
While the AFW system at the Ginna Nuclear Power Station is similar in design to the one at Turkey Point, the standby AFW system at Ginna was retrofitted to address a high energy line break (HELB) outside Containment event and thereby satisfies the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The system is supported by a safety-related ventilation system and powered by redundant Class lE electrical systems. In contrast, Turkey Points Standby Feedwater system is a non-safety grade system used for plant startup and shutdowns and is located in the outside environs.
Consequently, the OE included in the report was not deemed directly applicable.
The system is not relied upon to mitigate a HELB or any other postulated transient or accident, and though credited in select fire scenarios, its function as a backup to the AFW system in these scenarios is not subject to the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a LCO.
- The NRCs final policy statement on TS improvements (Reference 3) states that the Residual Heat Removal (RHR) system is one example of a system satisfying Criterion 4 of 10 CFR 50.36(c)(2)(ii) and thereby subject to inclusion as a TS LCO. In Standard Technical Specification (STS) 3.9.5 of NUREG-1431, Volume 2, Bases (Reference 4), the only description of the RHR system satisfying Criterion 4 is in MODE 6 with the reactor cavity water level 23 feet or more above the reactor vessel flange. The guidance explains that only one RHR train is required in this configuration because the water above the reactor vessel flange provides backup capability for decay heat removal. In essence, the single RHR train is credited as the primary means and the cavity water level as the backup means for maintaining fuel cladding integrity during this operational mode.
Turkey Point Nuclear Plant L-2017-188 Docket Nos. 50-250 and 50-251 Enclosure Page 4 of 4 In contrast, the highly reliable AFW trains are credited as the primary and backup means for decay heat removal capability during MODES 1, 2 and 3. In the event one AFW train is unavailable, the redundant AFW train is capable of performing its specified function. The non-safety grade Standby Feedwater System provides a shutdown function but not a safety-related or emergency function. Only for fires disabling all three AFW pumps is credit taken for the Standby Feedwater System. As stated earlier, fire scenarios are subject to a separate license condition and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for inclusion as a TS LCO. The FPP is not addressed in the TS other than to establish administrative controls consistent with other programs implemented by license condition.
References:
- 1. Jensen Hughes Report #: 033006-RPT-002, PTN NFPA 805 Implementation - Task 2 Monitoring - NFPA 805 Monitoring Program Phase 2/3: Screening and Risk Target Values, Revision 3, October 24, 2016
- 2. NUREG/CR-5764, Auxiliary Feedwater System Risk-Based Inspection Guide for the Ginna Nuclear Power Station, September 1991.
- 3. NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132)
- 4. NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0, Volume 2 Bases (Accession No. ML12100A228)