|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#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 |
| | |
| 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 | |
|
| |
|
| ==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 |
|
| |
|
| 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.
| |
| 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.
| |
| 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:== | | ==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 |
|
| |
|
| 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 | |
|
| |
|
| 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). |
|
| |
|
| 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. |
|
| |
|
| 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).
| |
| 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 system's 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 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
| |
| -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.
| |
| The NRC's 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:== | | ==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. ML12100A228)}} | | : 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 |
|---|
|
|
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
[Table View] |
|
|---|
Category:Letter type:L
MONTHYEARL-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024
Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-11-12012 November 2024
Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
L-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024
Radiological Emergency Plan Revision 77
L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024
Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024
Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024
Cycle 34 Core Operating Report
L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024
Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes
L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024
Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)
L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024
Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024
Submission of Periodic Reports
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024
Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02
L-2024-122, Core Operating Limits Report2024-08-12012 August 2024
Core Operating Limits Report
L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024
Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024
Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project
L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024
Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05
L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024
10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report
L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024
Cycle 33 Core Operating Limits Report
L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024
Cycle 34 Core Operating Limits Report
L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024
Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision
L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024
Radiological Emergency Plan Revision 76
L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024
Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02
L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024
Submittal of Periodic Reports
L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024
Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024
Proposed Use of a Subsequent ASME Code Edition and Addenda
L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024
Revised Steam Generator Tube Inspection Reports
L-2024-011, 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 Applications2024-03-13013 March 2024
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-2024-014, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024
2023 Annual Radioactive Effluent Release Report
L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024
Notification of Improved Standard Technical Specifications (ITS) Implementation
L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024
Supplement to 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-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 Owners Activity Report (OAR-1)2024-01-18018 January 2024
Inservice Inspection Program Owners 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-2023-172, 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 Owners Activity Report (OAR-1)2023-08-21021 August 2023
Inservice Inspection Program Owners 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)
2024-09-25
[Table view]
Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024
Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024
Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024
Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024
Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
ML24269A1292024-09-24024 September 2024
Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-110, 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-2018-191, 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-2018-218, 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-2018-193, 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
2024-09-24
[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)
