|
---|
Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[Table view] Category:Code Relief or Alternative
MONTHYEARML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21302A0902021-10-29029 October 2021 Verbal Authorization by the Office Nuclear Regulation Relief Request No. 10 Use of ASME Code Case N-513-4 for Extended Period Not to Exceed Six Months L-2021-107, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure2021-05-13013 May 2021 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure ML20308A7472020-12-0707 December 2020 Withdrawal of Request for Relief Concerning Train a and B Component Cooling Water Supply and Return Piping ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17082A5102017-04-0606 April 2017 Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval L-2017-050, Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 52017-03-22022 March 2017 Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 5 ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML13329A1202014-01-14014 January 2014 SE for RR No. 11 for 4th 10-Year Inservice Inspection Interval - Alternative Through-Wall Sizing Requirements for Implementation of ASME Code, Section XI, Appendix V111, Supplement 10 (TAC Nos. MF1391-92) L-2012-381, Fourth Ten-Year Interval, Relief Request No. 102012-11-13013 November 2012 Fourth Ten-Year Interval, Relief Request No. 10 L-2012-193, Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.72012-06-0505 June 2012 Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.7 ML1030502252010-11-0505 November 2010 Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair ML0533903272005-12-0606 December 2005 Relief Request, Safety Evaluation for Temporary Non-Code Repair of Spent Fuel Pool Cooling Line ML0520901822005-08-15015 August 2005 Relief, Regarding Mechanical Clamping Device on Pressure Boundary Piping ML0503503632005-03-0303 March 2005 Relief Request 1, Authorization of ISI Interval ML0428204702004-10-0606 October 2004 Safety Evaluation for Relief Requests PR-01 and PR-04 L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds2004-07-22022 July 2004 ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds ML0416100682004-06-0404 June 2004 Correction Ltr, RAI Regarding Fourth Interval Inservice Test Relief Requests ML0330404922003-10-31031 October 2003 Relaxation of the Requirements of Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections ML0306203852003-04-25025 April 2003 Relief, Associated with Reactor Vessel Closure Head Repair L-2003-063, ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 102003-03-10010 March 2003 ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 10 L-2002-085, Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 252002-05-0606 May 2002 Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 25 L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-4242002-03-0101 March 2002 Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424 2022-05-10
[Table view] |
Text
0 June 5, 2012 FPL. L-2012-193 POWERING TODAY. 10 CFR 50.55a EMPOWERING TOMORROW, U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Turkey Point Unit 4 Docket No. 50-251 Concrete Containment Inservice Inspection Program Exempt Tendon Inspection Relief Request No.7 In accordance with 10 CFR 50.55a (a)(3)(i), Florida Power and Light Company (FPL), is requesting relief for Turkey Point Unit 4, from ASME Section Xl Code, 2001 Edition, with Addenda through 2003, Paragraph IWL-2521.1(c), which requires that each exempted tendon shall be examined in accordance with IWL-2524 and IWL-2525 to the extent that the end anchorages of the exempt tendon are accessible either during operation or at an outage.
The tendon caps located near and above the Turkey Point Unit 4 discharge piping for the main steam safety and atmospheric dump and the steam generator blowdown to atmosphere are considered inaccessible during unit operation as a result of safety concerns for inspection p*ersonnel. In accordance with IWL-2521.1 any inaccessible tendon is designated as exempt.
FPL is requesting relief from the requirement to perform examinations at the inaccessible end of the designated exempt tendons during the Turkey Point Unit 4 2012 Fall refueling outage.
FPL seeks approval to perform substitute tendon examinations for Turkey Point Unit 4, following the Turkey Point Unit 3 tendon surveillance activities during the summer of 2012, without having to demobilize any inspection equipment or personnel already onsite.
Examinations of substitute tendons will provide sufficient information to assess the performance of the post-tensioning system subject to similar environmental conditions and prestressing requirements. As such, FPL proposes to perform alternative examinations to those in IWL-2521.1 (c) which will provide an acceptable level of quality and safety.
The attached Relief Request No. 7 for Turkey Point Unit 4 is submitted pursuant to 10 CFR 50.55a (a)(3)(i), since the proposed alternative examinations provide an acceptable level of quality and safety.
A similar Relief Request for Turkey Point Units 3 and 4 was previously approved by the Nuclear Regulatory Commission on October 20,1999. (TAC Nos. MA5239 and MA5240).
Approval of the attached Relief Request No.7 is requested by September 2012 to allow for rescheduling tendon examinations, if required.
an FPL Group company
L-201 1-193 Page 2 Should there be any questions concerning this submittal, please contact Mr. Robert J.
Tomonto, Licensing Manager, at (3""* 246-7327.
Sincerely, Michael Kiley Vice President Turkey Point Nuclear Plant S1I Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Ins-ector, USNRC, Turkey Point Plant
ATTACHMENT TO L-2012-193 FLORIDA POWER AND LIGHT TURKEY POINT UNIT 4 RELIEF REQUEST No. 7 EXEMPT TENDON INSPECTION
ATTACHMENT L-2012-193 EXEMPT TENDON INSPECTION RELIEF REQUEST No. 7 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
- 1. ASME CODE COMPONENTS AFFECTED Code Class CC Tendon Anchorage Areas, which are located at Buttress #5, on the west side of Buttresses #4 and #6 and at the ring girder above the Main Steam and Feedwater platforms at Turkey Point Unit 4. Category L-B, Unbonded Post-Tensioning System, Item Numbers L2.30, L2.40, and L2.50.
Approximately 142 hoop tendons and 65 dome tendons on each unit have one end considered inaccessible due to personnel safety. Tendon caps located near and above the discharge piping for the main steam safety and atmospheric dump and the steam generator blowdown to atmosphere are considered inaccessible during unit operation as a result of safety concerns for inspection personnel as determined by plant safety Specific tendons are selected on a random basis to be inspected in accordance with IWL-2521 during each surveillance interval. For the 40th Surveillance (IWL) Interval for Turkey Point Unit 4, the following four randomly-selected tendons fall within the ira-cessible tendon anchorage areas listed above: 1D20, 1D23, 2D20, and 51H40.
- 2. ASME CODE EDITION AND ADDENDA ASME Section Xl, 2001 Edition with Addenda through 2003, Subsection IWL.
- 3. APPLICABLE CODE REQUIREMENT The inspection requirements for the tendons are provided in ASME Section XI, 2001 Edition with Addenda through 2003, Subsection IWL. Specifically, Section IWL-2521 and Table IWL-2500-1 require the tendons to be inspected under the provisions of Category L-B, Unbonded Post-Tensioning System, Item Numbers L2.30, L2.40, and L2.50, where:
L2.30, which requires anchorage hardware and surrounding concrete to be examined in accordance with IWL-2524, and receive a detailed visual examination in accordance with IWL-231 0(b) extending 2 feet from the edge of the bearing plate, L2.40, which requires the corrosion protection medium to be examined in accordance with IWL-2525, and L2.50, which requires the amount of free water be examined in accordance with IWL-2525.
Section IWL-2521.1 permits the exemption from a full inspection of tendon anchorage areas that are not accessible for examination because of safety or radiological hazards or because of structural obstructions.
1 of 5
ATTACHMENT L-2012-193 EXEMPT TENDON INSPECTION RELIEF REQUEST No. 7 The following are the alternative inspection requirements for the exempt tendon anchorages:
" Paragraph 2521.1(c) requires that each exempted tendon be examined in accordance with IWL-2524 and IWL-2525 to the extent that the end anchorages of the exempt tendon are accessible either during operation or at an outage.
- IWL-2524 requires a visual examination of the tendon anchorage areas (anchorage hardware, including bearing plates, anchorheads, wedges, buttonheads, shims, and the concrete extending outward a distance of 2 feet from the edge of the bearing plate), and documentation of free water contained in the anchorage end cap as well as any which drains from the tendon during the examination process.
" IWL-2525 requires the collection of samples of the corrosion protection medium for laboratory analysis for reserve alkalinity, water content, and concentrations of water soluble chlorides, nitrates, and sulfides. In addition, IWL-2525 requires the collection of free water for laboratory analysis to determine pH level.
- 4. REASON FOR THE RELIEF REQUEST The tendon caps located near and above the Turkey Point Unit 4 discharge piping for the main steam safeties, atmospheric dumps and the steam generator blowdown to atmosphere are considered inaccessible during unit operation as a result of safety concerns for inspection personnel. Therefore, per IWL-2521.1, they are exempted.
Florida Power & Light Company (FPL) is requesting relief from the requirement to perform examinations at the inaccessible end of exempt tendons during the upcoming Turkey Point Unit 4 2012 Fall refueling outage. FPL seeks approval to perform substitute tendon examinations for Turkey Point Unit 4, following the Turkey Point Unit 3 tendon surveillance during the summer of 2012, without having to demobilize any inspection equipment or personnel already onsite.
The request will relieve FPL from the requirement to perform the examinations required by IWL-2524 and IWL-2525, (i.e., Table IWL-2500-1, Item Numbers L2.30, L2.40, and L2.50) at the inaccessible end of exempt tendons. Examinations at the other end of exempted tendons, accessible during plant operation, are not affected by this request.
FPL is requesting relief from a full inspection of tendon anchorage areas pursuant to Section IWL-2521.1(c) of ASME Section XI and 10 CFR 50.55a(a)(3)(i), by proposing alternative examinations that will provide an acceptable level of quality and safety.
The proposed alternative is to inspect two tendons as substitutes for each inaccessible tendon ends for the Turkey Point Unit 4 40th year surveillance.
In total, there are eight tendons selected for substitution of four exempt tendons that have been randomly selected. Dome tendons 1D34 and 1D35 have been selected as alternatives for 1D20; 1D42 and 1D<3 are alternates for 1D23; 2D01 and 2D09 are aiternates for 2D20; and 62H35 and 62H36 are alternatives for 51 H40.
2 of 5
ATTACHMENT L-2012-193 EXEMPT TENDON INSPECTION RELIEF REQUEST No. 7
- 5. PROPOSED ALTERNATIVE Pursuant to 10 CFR 50.55a(a)(3)i, FPL proposes an alternative to the Code requirements of IWL-2521.1(c) for the exempt tendons outlined in Section 1:
- 1. The accessible end of exempt tendons shall be examined in accordance with IWL-2524 and IWL-2525.
- 2. For each exempt tendon, an accessible substitute tendon within the same environment shall be selected and examined in accordance with IWL-2524 and IWL-2525.
- 3. In addition, an accessible tendon located as close as possible to each exempt tendon shall be examined at both ends in accordance with IWL-2524 and IWL-2525.
- 6. BASIS FOR USE The main purpose for examinations of the tendon anchorage areas, corrosion protection medium and free water during an outage (IWL-2524 and IWL-2525) would be to look for signs of corrosion in the tendon anchorage components and to assess the condition of the corrosion prevention medium and the concrete. During scheduled tendon inspections, these examnations are performed at many randomly selected tendons, and only relative few tendons in the sample are expected to be considered exempted due to personnel safety concerns. Furthermore, as stated in Relief Request 20 for the First Ten Yaar Interval, iKis statistically probable that up to three tendons on each unit may be exempt in any inspection period based on the number of tendons in the inaccessible area versus accessible tendons. This represents only 15% of the total number of tendons likely to be examined. The population of tendons that are non-exempt, plus the alternative examinations listed above, provide sufficient information to assess the performance of the entire post tensioning system given that each tendon is subject to similar environmental conditions and prestressing requirements.
To date, no significant anomalies have been noted with respect to corrosion of the tendon wires, anchorage components, or the corrosion prevention medium, in the general tendon population. The areas considered inaccessible are not subject to any unique conditions and selecting substitute tendons as close as possible to the exempt tendons will provide equivalent information as to the condition of the tendon caps. Several tendons located in the exclusion zone above the main steam platforms were examined during past inspections. These tendons were accessed primarily during an extended outage in which both Units 3 and 4 were shut down for in excess of one year. The results of these inspections were consistent with the results of tendons inspected in other locations.
The 30h and 3 5 th year inspections were performed in accordance with the approved Relief Request No. 20, issued by the NRC on October 20, 1999. As noted below, the results of these inspections demonstrated that the tendons were in compliance with the IWL requirements.
3 of 5
ATTACHMENT L-2012-193 EXEMPT TENDON INSPECTION RELIEF REQUEST No. 7 During the 30th Year Inspections, Unit 4 tendon 2D23 was randomly selected for inspection and subsequently determined to be exempt. Substitute tendons 2D5 and 2D6 were selected and examined for this exempt tendon. In addition, visual inspection of the accessible anchorage areas of tendon 2D23 was performed. The results of the 30th Year inspection demonstrated that the tendons met the applicable Section Xl requirements.
During the 35th Year Inspections, Unit 4 tendon 2D34 was randomly selected for inspection and subsequently determined to be exempt due to safety hazards as discussed in Sections 2 of this Relief Request. Unit 4 substitute tendons 2D07 and 2D08 were selected and examined for these exempt tendons. Visual inspections of the accessible anchorage area of tendon 2D34 met the applicable Section XI requirements. The results of the 35th Year inspection demonstrated that the tendons met the applicable Section XI requirements.
In the previously approved Relief Request 20, the Staff concluded that the licensee's alternative examination provides more stringent requirements than IWL requirements by providing examination of additional tendon anchorages exposed to a similar environment in close proximity to the randomly selected tendon that has been
(.-xempted due to safety concerns.
Based on the preceding information, the proposed alternative examinations will provide an acceptable level of quality and safety in lieu of the requirements of IWL-2521.1 (c). As stated above, this Relief Request is applicable for Turkey Point Unit 4 only.
- 7. DURATION OF PROPOSED ALTERNATIVE:
The duration of the proposed alternative will be for the 40th tendon inspections, for the 2 nd 10-Year Interval of the Concrete Containment Inservice Inspection Program, 12-1SI/IWL-PTN-3/4, for Turkey Point Unit 4.
- 8. PRECEDENTS Similar relief was requested by Florida Power and Light Company for Turkey Point Units 3 and 4 for the First Ten-Year interval per Relief Request 20. Relief was granted by the NRC pursuant to 10 CFR 50.55a(a)(3)(i) per Safety Evaluation dated October 20,1999, (TAC Nos. MA-5239 and MA 5240)
- 9. ATTACHMENTS TO RELIEF REQUEST 7 Figure 1 Partial site plan Figure 2 Photo depicting location of exempt tendon 4 of 5
ATTACHMENT L-2012-193 EXEMPT TENDON INSPECTION RELIEF REQUEST No. 7 Figure 1: Partial Site Plan. The area between Buttress 4 and 5 for Unit 4 are considered inaccessible when Unit 4 is online.
Figure 2: Photos depicting relation of main steam safety valve tailpipes, atmospheric dump valve arid the Unit 4 Containment t5 of 5