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| {{#Wiki_filter:June 16, 2006Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 | | {{#Wiki_filter:June 16, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONALINFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206) | | TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206) |
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| ==Dear Mr. Stall:== | | ==Dear Mr. Stall:== |
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| By letter dated February 20, 2006, Florida Power & Light Company requested relief from certainrequirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4. | | By letter dated February 20, 2006, Florida Power & Light Company requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review. |
| | This request was discussed with members of your staff on June 1, and on June 14, 2006, Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974. |
| | Sincerely, |
| | /RA/ |
| | Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251 |
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| The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review.This request was discussed with members of your staff on June 1, and on June 14, 2006,Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974.Sincerely, /RA/Brendan T. Moroney, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-250 and 50-251
| | ==Enclosure:== |
| | As stated cc w/encl: See next page |
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| ==Enclosure:==
| | June 16, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 |
| As stated cc w/encl: See next page June 16, 2006Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
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| ==SUBJECT:== | | ==SUBJECT:== |
| TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONALINFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206) | | TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206) |
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| ==Dear Mr. Stall:== | | ==Dear Mr. Stall:== |
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| By letter dated February 20, 2006, Florida Power & Light Company requested relief from certainrequirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4. | | By letter dated February 20, 2006, Florida Power & Light Company requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4. |
| | | The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review. |
| The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review.This request was discussed with members of your staff on June 1, and on June 14, 2006,Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974.Sincerely, /RA/Brendan T. Moroney, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-250 and 50-251 | | This request was discussed with members of your staff on June 1, and on June 14, 2006, Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974. |
| | Sincerely, |
| | /RA/ |
| | Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: See next page Distribution:PUBLICLPL2-2 R/FRidsNrrPMBMoroneyRidsNrrDorlLpl2-2RidsNrrLABClaytonRidsNrrDciCpnb RidsOgcRpRidsRgn2MailCenter RidsAcrsAcnwMailCenterTLupold, NRRADAMS ACCESSION No.: ML061590235 NRR-088OFFICELPL2-2/PMLPL2-2/LACPNB/BCLPL2-2/BCNAMEBMoroneyBClaytonTChanby memo datedMMarshallDATE6/14/066/14/0605/30/066/16/06OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATIONTURKEY POINT UNITS 3 AND 4RELIEF REQUEST NOS. 1A, 14A, AND 15ADOCKET NOS. 50-250 AND 50-251General1.Relief Requests 1A, 14A and 15A indicated that the third 10-year inservice inspection (ISI) interval ended February 21, 2004, for Unit 3 and April 14, 2004, for Unit 4. By letter dated October 20, 2004, the NRC authorized extension of the third 10-year interval toFebruary 21, 2005, for Unit 3 and to April 14, 2005, for Unit 4. Please indicate the proper end dates for the Unit 3 and Unit 4 third 10-year ISI intervals.Relief Request 1A | | As stated cc w/encl: See next page Distribution: |
| :2.In Florida Power and Light Company (FPL) letter dated February 20, 2006, it is statedthe objective of Relief Request 1A is to resubmit the previously approved Relief Request No.1. The request also states that this revision submits the examination volume coverage obtained during the third 10-year ISI interval inspection. In comparing Relief Request 1 with Relief Request 1A, the upper shell-to-flange weld is included in both requests. Welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C are included in Relief Request 1, but they are not included in relief request 1A. Relief Request 1A contains additional examinations that had limited coverage, welds 3-WR-9 and 4-WR-9 and the 1-inch annular surface of flange surrounding each reactor vessel stud hole.Does Relief Request 1A supersede Relief Request 1, or is it in addition to ReliefRequest 1? If Relief Request 1A is to supersede Relief Request 1, was essentially full coverage obtained on welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C? If Relief Request 1A is to be in addition to Relief Request 1, is the request for relief with regard to welds 3-WR-18 and 4-WR-18 any different than the request for relief made under Relief Request 1 (other than 71-percent coverage was obtained vs. 68-percent projected)? 3.Relief Request 1A states that the examination of the Figure1 IWB-2500-12 A-B-C-D-E-F-G-H volume is limited when scanning the carbon steel base material surrounding the stud holes due to the sealing surfaces configuration. Please explain how the sealing surfaces configuration limits access to the required examination volume, and whether any alternate scanning angles can be used to achieve coverage in this area.Relief Request 14A
| | PUBLIC LPL2-2 R/F RidsNrrPMBMoroney RidsNrrDorlLpl2-2 RidsNrrLABClayton RidsNrrDciCpnb RidsOgcRp RidsRgn2MailCenter RidsAcrsAcnwMailCenter TLupold, NRR ADAMS ACCESSION No.: ML061590235 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA CPNB/BC LPL2-2/BC NAME BMoroney BClayton TChan MMarshall by memo dated DATE 6/14/06 6/14/06 05/30/06 6/16/06 OFFICIAL RECORD COPY |
| :4.FPL letter dated February 20, 2006, states the objective of Relief Requests 14A and15A is to resubmit the previously approved Relief Request 14 and 15 for Class 1 and 2 vessel inside radius, vessel welds, and piping welds that did not receive code-required volume. In comparing Relief Request 14 and Relief Request 14A, there are four components (29"-RCS-1305-3, 8"-SI-2309-22, 8"-SI-2309-24, and 6"-BDA-2301-8) that are listed in Relief Request 14 but not in Relief Request 14A. Please explain why the four components are not included in Relief Request 14A. 5.In Relief Request 14, component 3-SRGN-01-IR is listed under examinationcategory B-D, item No. B3.120, which is applicable to the Pressurizer. In Relief Request 14A, component 3-SRGN-01-IR is listed as applicable to examination category B-D, item No. B3.140. Please explain this change in classification of component 3-RGN-01-IR.6.Table 1 identifies the applicable code requirement for component "Spray Nozzle-SP-03-1-IR" as examination category B-D, item No. B3.140, which is applicable to steam generators. Please clarify whether this is a pressurizer spray nozzle or if it is applicable to steam generators.7. Table 1 of Relief Request 14A indicates 66-percent coverage from the elbow side forcomponent 31"-RCS-1302-10 was achieved. Relief Request 14 indicates 75-percent coverage from the elbow side for component 31"-RCS-1302-10 was achieved. Please explain the difference in coverage reported between the FPL August 8, 1996, letter andthe February 20, 2006, letter.8.Describe any flaws or relevant indications identified adjacent to the areas that could notbe examined.
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| Relief Request 15A | | REQUEST FOR ADDITIONAL INFORMATION TURKEY POINT UNITS 3 AND 4 RELIEF REQUEST NOS. 1A, 14A, AND 15A DOCKET NOS. 50-250 AND 50-251 General |
| :9.Describe any flaws or relevant indications identified adjacent to the areas that could notbe examined. | | : 1. Relief Requests 1A, 14A and 15A indicated that the third 10-year inservice inspection (ISI) interval ended February 21, 2004, for Unit 3 and April 14, 2004, for Unit 4. By letter dated October 20, 2004, the NRC authorized extension of the third 10-year interval to February 21, 2005, for Unit 3 and to April 14, 2005, for Unit 4. Please indicate the proper end dates for the Unit 3 and Unit 4 third 10-year ISI intervals. |
| Mr. J. A. StallTURKEY POINT PLANT Florida Power and Light Company cc:Mr. William E. Webster Vice President, Nuclear Operations Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
| | Relief Request 1A: |
| | : 2. In Florida Power and Light Company (FPL) letter dated February 20, 2006, it is stated the objective of Relief Request 1A is to resubmit the previously approved Relief Request No.1. The request also states that this revision submits the examination volume coverage obtained during the third 10-year ISI interval inspection. In comparing Relief Request 1 with Relief Request 1A, the upper shell-to-flange weld is included in both requests. Welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C are included in Relief Request 1, but they are not included in relief request 1A. Relief Request 1A contains additional examinations that had limited coverage, welds 3-WR-9 and 4-WR-9 and the 1-inch annular surface of flange surrounding each reactor vessel stud hole. |
| | Does Relief Request 1A supersede Relief Request 1, or is it in addition to Relief Request 1? If Relief Request 1A is to supersede Relief Request 1, was essentially full coverage obtained on welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C? If Relief Request 1A is to be in addition to Relief Request 1, is the request for relief with regard to welds 3-WR-18 and 4-WR-18 any different than the request for relief made under Relief Request 1 (other than 71-percent coverage was obtained vs. 68-percent projected)? |
| | : 3. Relief Request 1A states that the examination of the Figure1 IWB-2500-12 A-B-C-D-E-F-G-H volume is limited when scanning the carbon steel base material surrounding the stud holes due to the sealing surfaces configuration. Please explain how the sealing surfaces configuration limits access to the required examination volume, and whether any alternate scanning angles can be used to achieve coverage in this area. |
| | Relief Request 14A: |
| | : 4. FPL letter dated February 20, 2006, states the objective of Relief Requests 14A and 15A is to resubmit the previously approved Relief Request 14 and 15 for Class 1 and 2 vessel inside radius, vessel welds, and piping welds that did not receive code-required volume. In comparing Relief Request 14 and Relief Request 14A, there are four components (29"-RCS-1305-3, 8"-SI-2309-22, 8"-SI-2309-24, and 6"-BDA-2301-8) that are listed in Relief Request 14 but not in Relief Request 14A. Please explain why the four components are not included in Relief Request 14A. |
| | : 5. In Relief Request 14, component 3-SRGN-01-IR is listed under examination category B-D, item No. B3.120, which is applicable to the Pressurizer. In Relief Request 14A, component 3-SRGN-01-IR is listed as applicable to examination category B-D, item No. B3.140. Please explain this change in classification of component 3-RGN-01-IR. |
| | : 6. Table 1 identifies the applicable code requirement for component Spray Nozzle-SP 1-IR as examination category B-D, item No. B3.140, which is applicable to steam generators. Please clarify whether this is a pressurizer spray nozzle or if it is applicable to steam generators. |
| | : 7. Table 1 of Relief Request 14A indicates 66-percent coverage from the elbow side for component 31"-RCS-1302-10 was achieved. Relief Request 14 indicates 75-percent coverage from the elbow side for component 31"-RCS-1302-10 was achieved. Please explain the difference in coverage reported between the FPL August 8, 1996, letter and the February 20, 2006, letter. |
| | : 8. Describe any flaws or relevant indications identified adjacent to the areas that could not be examined. |
| | Relief Request 15A: |
| | : 9. Describe any flaws or relevant indications identified adjacent to the areas that could not be examined. |
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| Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW.
| | Mr. J. A. Stall TURKEY POINT PLANT Florida Power and Light Company cc: |
| Suite 220 Washington, DC 20004T. O. Jones, Site Vice PresidentTurkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035 County Manager Miami-Dade County 111 Northwest 1 Street, 29th Floor Miami, Florida 33128 Senior Resident InspectorTurkey Point Nuclear Plant U.S. Nuclear Regulatory Commission 9762 SW. 344 th StreetFlorida City, Florida 33035Mr. William A. Passetti, ChiefDepartment of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741Mr. Craig Fugate, DirectorDivision of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304Michael O. PearcePlant General Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035Walter ParkerLicensing Manager Turkey Point Nuclear Plant 9760 SW 344th Street Florida City, FL 33035Mark Warner, Vice PresidentNuclear Operations Support Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. Rajiv S. KundalkarVice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420}}
| | Mr. William E. Webster Mr. Craig Fugate, Director Vice President, Nuclear Operations Division of Emergency Preparedness Florida Power & Light Company Department of Community Affairs P.O. Box 14000 2740 Centerview Drive Juno Beach, FL 33408-0420 Tallahassee, Florida 32399-2100 Attorney General M. S. Ross, Managing Attorney Department of Legal Affairs Florida Power & Light Company The Capitol P.O. Box 14000 Tallahassee, Florida 32304 Juno Beach, FL 33408-0420 Michael O. Pearce Marjan Mashhadi, Senior Attorney Plant General Manager Florida Power & Light Company Turkey Point Nuclear Plant 801 Pennsylvania Avenue, NW. Florida Power and Light Company Suite 220 9760 SW. 344th Street Washington, DC 20004 Florida City, FL 33035 T. O. Jones, Site Vice President Walter Parker Turkey Point Nuclear Plant Licensing Manager Florida Power and Light Company Turkey Point Nuclear Plant 9760 SW. 344th Street 9760 SW 344th Street Florida City, FL 33035 Florida City, FL 33035 County Manager Mark Warner, Vice President Miami-Dade County Nuclear Operations Support 111 Northwest 1 Street, 29th Floor Florida Power and Light Company Miami, Florida 33128 P.O. Box 14000 Juno Beach, FL 33408-0420 Senior Resident Inspector Turkey Point Nuclear Plant Mr. Rajiv S. Kundalkar U.S. Nuclear Regulatory Commission Vice President - Nuclear Engineering 9762 SW. 344th Street Florida Power & Light Company Florida City, Florida 33035 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741}} |
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Category:Letter
MONTHYEARL-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
ML24262A2272024-09-18018 September 2024
Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles
IR 05000250/20243012024-09-18018 September 2024
NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301
ML24158A0052024-09-17017 September 2024
Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses
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
ML24207A0342024-09-13013 September 2024
– Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter
ML24256A1132024-09-13013 September 2024
Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request
IR 05000250/20240052024-08-23023 August 2024
Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005
ML24234A0062024-08-22022 August 2024
Project Manager Assignment
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
IR 05000250/20240112024-08-0606 August 2024
Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
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
ML24184B2822024-07-16016 July 2024
– Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
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-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024
Condition Prohibited by Technical Specifications
ML24173A1902024-06-28028 June 2024
Withdrawal of an Amendment Request
ML24159A2652024-06-26026 June 2024
Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project
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
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
IR 05000250/20244012024-06-0505 June 2024
– Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401
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
IR 05000250/20240012024-05-10010 May 2024
Integrated Inspection Report 05000250/2024001 and 05000251/2024001
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
ML24127A1862024-05-0909 May 2024
Request for Withholding Information from Public Disclosure
ML24135A0942024-05-0909 May 2024
Periodic Update to the Updated Final Safety Analysis Report
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024
Cycle 33 Core Operating Limits Report
IR 05000250/20240102024-05-0101 May 2024
Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation
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-2024-057, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024
0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications
ML24087A1992024-04-0505 April 2024
Achp Section 106 Letter Re Notice of Availability of the Final Environmental Impact Statement for Turkey Point Units 3 & 4 Subsequent License Renewal Application
ML24096A2162024-04-0505 April 2024
Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point
ML24087A1982024-04-0505 April 2024
Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application
ML24096A2182024-04-0505 April 2024
Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point
ML24096A2152024-04-0505 April 2024
Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point
ML24087A2012024-04-0505 April 2024
Letter to Talbert Cypress, Miccosukee Tribe of Indians of Florida; Re., Section 106 Letters for Turkey Point
ML24087A2002024-04-0505 April 2024
Letter to Miami-Dade County Office of Historic Preservation Re Section 106 on Turkey Point Units 3 & 4 EIS
ML24096A2142024-04-0505 April 2024
Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point
ML24072A2832024-04-0101 April 2024
Ltr to Dianne Strand-Notice of Avail.-Final Site-Specific Supp. 5a, 2nd Renewal to the GEIS for License Renewal
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
2024-09-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24261B8062024-09-17017 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24250A0242024-09-0606 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24250A0852024-09-0606 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24234A0842024-08-21021 August 2024
Notification of Inspection and Request for Information
ML24234A0142024-08-20020 August 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Spent Fuel Storage License Amendment Request (LAR) (L-2023-LLA-0142)
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
ML23226A0752023-08-14014 August 2023
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128)
ML23173A1522023-06-22022 June 2023
Request for Additional Information NextEra Fleet Emergency Plan Amendment Request
ML23129A8322023-05-0505 May 2023
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128)
ML23038A1892023-02-0303 February 2023
RP RFI April 2023
ML22311A5582022-11-22022 November 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep
ML22311A4752022-11-0707 November 2022
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - ITS
IR 05000250/20234012022-10-19019 October 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000250/2023401 and 05000251/2023401
ML22255A0502022-09-15015 September 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Replace Instrumentation with Digital Systems
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2024-09-06
[Table view] |
Text
June 16, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206)
Dear Mr. Stall:
By letter dated February 20, 2006, Florida Power & Light Company requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4.
The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review.
This request was discussed with members of your staff on June 1, and on June 14, 2006, Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
As stated cc w/encl: See next page
June 16, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT PLANT, UNITS 3 AND 4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 1A, 14A AND 15A (TAC NOS. MD0205 AND MD0206)
Dear Mr. Stall:
By letter dated February 20, 2006, Florida Power & Light Company requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, due to limitations that were identified during the third 10-year inservice inspection interval at Turkey Point Units 3 and 4.
The U.S. Nuclear Regulatory Commission staff has reviewed your requests and finds that a response to the enclosed Request for Additional Information is needed before we can complete the review.
This request was discussed with members of your staff on June 1, and on June 14, 2006, Ms. Stavroula Mihalakea agreed that a response would be provided within 30 days of the date of this letter. If you have any questions, please contact me at (301) 415-3974.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
As stated cc w/encl: See next page Distribution:
PUBLIC LPL2-2 R/F RidsNrrPMBMoroney RidsNrrDorlLpl2-2 RidsNrrLABClayton RidsNrrDciCpnb RidsOgcRp RidsRgn2MailCenter RidsAcrsAcnwMailCenter TLupold, NRR ADAMS ACCESSION No.: ML061590235 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA CPNB/BC LPL2-2/BC NAME BMoroney BClayton TChan MMarshall by memo dated DATE 6/14/06 6/14/06 05/30/06 6/16/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION TURKEY POINT UNITS 3 AND 4 RELIEF REQUEST NOS. 1A, 14A, AND 15A DOCKET NOS. 50-250 AND 50-251 General
- 1. Relief Requests 1A, 14A and 15A indicated that the third 10-year inservice inspection (ISI) interval ended February 21, 2004, for Unit 3 and April 14, 2004, for Unit 4. By letter dated October 20, 2004, the NRC authorized extension of the third 10-year interval to February 21, 2005, for Unit 3 and to April 14, 2005, for Unit 4. Please indicate the proper end dates for the Unit 3 and Unit 4 third 10-year ISI intervals.
Relief Request 1A:
- 2. In Florida Power and Light Company (FPL) letter dated February 20, 2006, it is stated the objective of Relief Request 1A is to resubmit the previously approved Relief Request No.1. The request also states that this revision submits the examination volume coverage obtained during the third 10-year ISI interval inspection. In comparing Relief Request 1 with Relief Request 1A, the upper shell-to-flange weld is included in both requests. Welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C are included in Relief Request 1, but they are not included in relief request 1A. Relief Request 1A contains additional examinations that had limited coverage, welds 3-WR-9 and 4-WR-9 and the 1-inch annular surface of flange surrounding each reactor vessel stud hole.
Does Relief Request 1A supersede Relief Request 1, or is it in addition to Relief Request 1? If Relief Request 1A is to supersede Relief Request 1, was essentially full coverage obtained on welds 3-DO-A, 3-DO-B, 3-DO-C, 4-DO-A, 4-DO-B, 4-DO-C? If Relief Request 1A is to be in addition to Relief Request 1, is the request for relief with regard to welds 3-WR-18 and 4-WR-18 any different than the request for relief made under Relief Request 1 (other than 71-percent coverage was obtained vs. 68-percent projected)?
- 3. Relief Request 1A states that the examination of the Figure1 IWB-2500-12 A-B-C-D-E-F-G-H volume is limited when scanning the carbon steel base material surrounding the stud holes due to the sealing surfaces configuration. Please explain how the sealing surfaces configuration limits access to the required examination volume, and whether any alternate scanning angles can be used to achieve coverage in this area.
Relief Request 14A:
- 4. FPL letter dated February 20, 2006, states the objective of Relief Requests 14A and 15A is to resubmit the previously approved Relief Request 14 and 15 for Class 1 and 2 vessel inside radius, vessel welds, and piping welds that did not receive code-required volume. In comparing Relief Request 14 and Relief Request 14A, there are four components (29"-RCS-1305-3, 8"-SI-2309-22, 8"-SI-2309-24, and 6"-BDA-2301-8) that are listed in Relief Request 14 but not in Relief Request 14A. Please explain why the four components are not included in Relief Request 14A.
- 5. In Relief Request 14, component 3-SRGN-01-IR is listed under examination category B-D, item No. B3.120, which is applicable to the Pressurizer. In Relief Request 14A, component 3-SRGN-01-IR is listed as applicable to examination category B-D, item No. B3.140. Please explain this change in classification of component 3-RGN-01-IR.
- 6. Table 1 identifies the applicable code requirement for component Spray Nozzle-SP 1-IR as examination category B-D, item No. B3.140, which is applicable to steam generators. Please clarify whether this is a pressurizer spray nozzle or if it is applicable to steam generators.
- 7. Table 1 of Relief Request 14A indicates 66-percent coverage from the elbow side for component 31"-RCS-1302-10 was achieved. Relief Request 14 indicates 75-percent coverage from the elbow side for component 31"-RCS-1302-10 was achieved. Please explain the difference in coverage reported between the FPL August 8, 1996, letter and the February 20, 2006, letter.
- 8. Describe any flaws or relevant indications identified adjacent to the areas that could not be examined.
Relief Request 15A:
- 9. Describe any flaws or relevant indications identified adjacent to the areas that could not be examined.
Mr. J. A. Stall TURKEY POINT PLANT Florida Power and Light Company cc:
Mr. William E. Webster Mr. Craig Fugate, Director Vice President, Nuclear Operations Division of Emergency Preparedness Florida Power & Light Company Department of Community Affairs P.O. Box 14000 2740 Centerview Drive Juno Beach, FL 33408-0420 Tallahassee, Florida 32399-2100 Attorney General M. S. Ross, Managing Attorney Department of Legal Affairs Florida Power & Light Company The Capitol P.O. Box 14000 Tallahassee, Florida 32304 Juno Beach, FL 33408-0420 Michael O. Pearce Marjan Mashhadi, Senior Attorney Plant General Manager Florida Power & Light Company Turkey Point Nuclear Plant 801 Pennsylvania Avenue, NW. Florida Power and Light Company Suite 220 9760 SW. 344th Street Washington, DC 20004 Florida City, FL 33035 T. O. Jones, Site Vice President Walter Parker Turkey Point Nuclear Plant Licensing Manager Florida Power and Light Company Turkey Point Nuclear Plant 9760 SW. 344th Street 9760 SW 344th Street Florida City, FL 33035 Florida City, FL 33035 County Manager Mark Warner, Vice President Miami-Dade County Nuclear Operations Support 111 Northwest 1 Street, 29th Floor Florida Power and Light Company Miami, Florida 33128 P.O. Box 14000 Juno Beach, FL 33408-0420 Senior Resident Inspector Turkey Point Nuclear Plant Mr. Rajiv S. Kundalkar U.S. Nuclear Regulatory Commission Vice President - Nuclear Engineering 9762 SW. 344th Street Florida Power & Light Company Florida City, Florida 33035 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741
