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| | issue date = 08/24/2009 | | | issue date = 08/24/2009 |
| | title = Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 | | | title = Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 |
| | author name = Boyce T H | | | author name = Boyce T |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Swafford P D | | | addressee name = Swafford P |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259 | | | docket = 05000259 |
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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 24, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT-UNIT 1, THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM RELATED TO ASME CODE CASE N-504-3, ALTERNATIVE RULES FOR REPAIR OF CLASSES 1,2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME0155) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: BROWNS FERRY NUCLEAR PLANT-UNIT 1, THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM RELATED TO ASME CODE CASE N-504-3, ALTERNATIVE RULES FOR REPAIR OF CLASSES 1,2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME0155) |
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| ==Dear Mr. Swafford:== | | ==Dear Mr. Swafford:== |
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| By letter dated November 25,2008, the Tennessee Valley Authority (TVA, the licensee) submitted Relief Request (RR) 1-ISI-22 requesting relief'from the requirements specified in the American Society of Mechanical Engineers (ASME) Code, Section XI for repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping weld overlays under Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i) for the Browns Ferry Nuclear Plant (BFN), Unit 1. The request proposed that in lieu of the requirements of the ASME Code, Case N-504-3, Paragraph (h), performing a system hydrostatic test, proposed an alternative to perform a system leakage test at normal operating pressure and temperature. | | By letter dated November 25,2008, the Tennessee Valley Authority (TVA, the licensee) submitted Relief Request (RR) 1-ISI-22 requesting relief'from the requirements specified in the American Society of Mechanical Engineers (ASME) Code, Section XI for repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping weld overlays under Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i) for the Browns Ferry Nuclear Plant (BFN), Unit 1. The request proposed that in lieu of the requirements of the ASME Code, Case N-504-3, Paragraph (h), |
| The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided in TVA's November 25,2008, letter. The NRC staff concluded that the proposed alternative described in the licensee's letter provides an acceptable level of quality and safety. Therefore, RR-1-ISI-22 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Browns Ferry Nuclear Plant, Unit 1. All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. | | performing a system hydrostatic test, proposed an alternative to perform a system leakage test at normal operating pressure and temperature. |
| P. Swafford -2 This relief is authorized for the remainder of the second 1 O-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1, 2017. Sincerely, Docket No. 50-259 | | The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided in TVA's November 25,2008, letter. The NRC staff concluded that the proposed alternative described in the licensee's letter provides an acceptable level of quality and safety. |
| | Therefore, RR-1-ISI-22 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Browns Ferry Nuclear Plant, Unit 1. All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. |
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| | P. Swafford -2 This relief is authorized for the remainder of the second 1O-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1, 2017. |
| | Sincerely, Docket No. 50-259 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Safety Evaluation cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST 1-ISI-22 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 | | Safety Evaluation cc w/encl: Distribution via Listserv |
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| ==1.0 INTRODUCTION==
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST 1-ISI-22 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 |
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| By letter dated November 25, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083380201), the Tennessee Valley Authority (TVA, the licensee), requested relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) requirements at Browns Ferry Nuclear Plant, Unit 1 (BFN). As an alternative to the ASME Code requirements, TVA proposed to implement a full structural weld overlay (FSWOL) repair in accordance with ASME Code Case N-504-3, Alternative Rules for Repair of Class 1, 2, and 3, "Austenitic Stainless Steel Piping, Section XI, Division 1," as modified by TVA in its submitlalletters.
| | ==1.0 INTRODUCTION== |
| The alternative documented in Relief Request (RR) 1-ISI-22 would be used to perform a leak test in lieu of a hydrostatic test on the FSWOL applied to the reactor pressure vessel (RPV) Feedwater N-1'1 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld. Although, the licensee has already implemented the installation of the FSWOL prior to the issuance of this safety evaluation (SE), this SE is being issued to document the decision made by the U.S. Nuclear Regulatory Commission (NRC) staff to grant the licensee's request by verbal authorization on November 26,2008. The NRC staff's memorandum dated December 12,2008 (ADAMS Accession No. ML083390526), reflects the basis for verbal approval.
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| ==2.0 REGULATORY EVALUATION==
| | By letter dated November 25, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083380201), the Tennessee Valley Authority (TVA, the licensee), |
| | requested relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) requirements at Browns Ferry Nuclear Plant, Unit 1 (BFN). |
| | As an alternative to the ASME Code requirements, TVA proposed to implement a full structural weld overlay (FSWOL) repair in accordance with ASME Code Case N-504-3, Alternative Rules for Repair of Class 1, 2, and 3, "Austenitic Stainless Steel Piping, Section XI, Division 1," as modified by TVA in its submitlalletters. The alternative documented in Relief Request (RR) 1-ISI-22 would be used to perform a leak test in lieu of a hydrostatic test on the FSWOL applied to the reactor pressure vessel (RPV) Feedwater N-1'1 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld. |
| | Although, the licensee has already implemented the installation of the FSWOL prior to the issuance of this safety evaluation (SE), this SE is being issued to document the decision made by the U.S. Nuclear Regulatory Commission (NRC) staff to grant the licensee's request by verbal authorization on November 26,2008. The NRC staff's memorandum dated December 12,2008 (ADAMS Accession No. ML083390526), reflects the basis for verbal approval. |
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| Pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supportS) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code, Section XI, Rules for In service Inspection (lSI) of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
| | ==2.0 REGULATORY EVALUATION== |
| The regulations require that inservice examination of components and system pressure tests conducted during the "first ten-year lSI interval and subsequent intervals comply Enclosure with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. BFN, Unit 1 second 1 O-year lSI interval is scheduled to end on June 1, 2017. The lSI Code of record for BFN for the second 10-year lSI interval is the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. Pursuant to 10 CFR 50.55a(a)(3), alternatives to requirements may be authorized if the licensee demonstrates that: (i) the proposed alternatives provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. TVA, submitted the subject relief request, pursuant to 10 CFR 50.55a(a)(3)(i), which proposed an alternative to the implementation of the ASME Code, Section XI requirements based on ASME Code Case N-504-3, the deposition of a FSWOL for the remaining service life of the identified components.
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| ASME Code Case N-504-3 was conditionally accepted by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," issued in October 2007. In RG 1.147, Revision 15, the NRC accepted ASME Code Case N-504-3 with the condition that the inspection requirements of ASME Code, Section XI, Nonmandatory Appendix Q, "Weld Overlay Repair of Class 1,2, and 3 Austenitic Stainless Steel Piping Weldments," shall be met as part of the installation and inspection of the weld overlay. 3.0 TECHNICAL EVALUATION 3.1 ASME Code Requirements for which Relief is Requested The lSI Code of record for BFN for the second 10-year lSI interval was the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. Consistent with IWA-4220, repairs shall be performed in accordance with the licensee's design specification and the original Construction Code. Later editions and addenda of the Construction Code or of ASME Code, Section III, either in their entirety or portions thereof, and ASME Code Cases may be used. In this case, the licensee proposed to implement a weld overlay repair in accordance with ASME Code Case N-504-3 as modified by the condition placed on the code case in RG 1.147, Revision 15 and the approved alternatives.
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| ===3.2 Duration===
| | Pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supportS) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code, Section XI, Rules for Inservice Inspection (lSI) of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the "first ten-year lSI interval and subsequent intervals comply Enclosure |
| of Relief Request This relief request for Unit 1 is applicable to its second 1 O-year lSI interval that is scheduled to end on June 1,2017. 3.3 Licensee's Proposed Alternative to ASME Code Case N-504-3 ASME Code Case N-504-3, Requirement (h) specifies that a hydrostatic test be performed in accordance with ASME Code, Section XI, IWA-5000 if the flaw penetrates the original pressure boundary.
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| As an alternative, leak testing in accordance with IWA-5000 at nominal operating pressure and temperature in lieu of the system hydrostatic testing will be performed.
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| -3 3.4 Licensee's Justification for the Proposed Alternative Licensee stated in their justification for the granting of relief that, the stresses generated in the material during the system leak test at nominal operating pressure is less than 30 percent of the allowable stress and the stress generated by the hydrostatic pressure test was in the low 30-percent region of the allowable stress for that material.
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| Material stress conditions in these ranges would not tend to drive flaw growth to such an extent that leakage would be generated or significantly increased.
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| Therefore, no significant observable differences would be provided by the performance of the hydrostatic test and the system leakage test would provide an acceptable alternative.
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| On this technical basis, hydrostatic test requirements were deleted from ASME Code Cases N-416, "Alternative Pressure Test Requirement for Welded or Brazed Joints for Replacement Parts and Piping Subassemblies, or Installation of Replacement Items by Welding or Brazing, Classes 1, 2, and 3 Section XI, Division 1," and N-498, "Alternative Requirements for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems Section XI, Division 1." The use of a system leak test at nominal operating pressure in lieu of a hydrostatic test has been incorporated in ASME Code, Section XI beginning in the 1998 Edition with the 1999 Addenda. Therefore, the licensee determined that this alternative provides an acceptable level of quality and safety. 3.5 Evaluation The licensee's proposed modification to Requirement (h) of ASME Code Case N-504-3 was to perform a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in accordance with ASME Code, Section XI (2001 Edition with the 2003 Addenda), IWA-5000 and, by reference, ASME Code, Section XI, IWB-5000.
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| Precedence for use of a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in lieu of a hydrostatic test, which would be conducted at a higher pressure, has been set with ASME Code Case N-416-1. ASME Code Case N-416-1 was accepted by the NRC staff in RG 1.147 and has been incorporated into ASME Code, Section XI beginning in the 1998 Edition with the 1999 Addenda. Unit 1 is currently in its second 10-year lSI interval and the lSI Code of record for this interval is the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. The NRC staff reviewed the licensee's justification for the proposed alternative and finds it acceptable based on the following: since similar stresses are produced in the material during a system leak test at the nominal operating pressure corresponding to 1 OO-percent rated reactor power or during the hydrostatic test, any leakage that would otherwise occur during operation due to an existing defect will be identified regardless of the type of test (Le., hydrostatic test or system leak test) that is performed on the weld overlay, substitution of a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power for a hydrostatic test was incorporated in ASME Code, Section XI, 1998 Edition, 1999 Addenda, and
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| -4TVA, the licensee's alternative is consistent with the current industry practice, and a similar request by the license holder for the Cooper Nuclear Station was approved by the NRC staff in its letter dated August 15, 2008. Based on the above, the NRC staff determined that TVA, the licensee's proposed alternative to perform a system leak test at the nominal operating pressure corresponding to 1 OO-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety.
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| ==4.0 CONCLUSION==
| | -2 with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. BFN, Unit 1 second 1O-year lSI interval is scheduled to end on June 1, 2017. The lSI Code of record for BFN for the second 10-year lSI interval is the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. |
| | Pursuant to 10 CFR 50.55a(a)(3), alternatives to requirements may be authorized if the licensee demonstrates that: (i) the proposed alternatives provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. TVA, submitted the subject relief request, pursuant to 10 CFR 50.55a(a)(3)(i), which proposed an alternative to the implementation of the ASME Code, Section XI requirements based on ASME Code Case N-504-3, the deposition of a FSWOL for the remaining service life of the identified components. |
| | ASME Code Case N-504-3 was conditionally accepted by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," |
| | issued in October 2007. In RG 1.147, Revision 15, the NRC accepted ASME Code Case N-504-3 with the condition that the inspection requirements of ASME Code, Section XI, Nonmandatory Appendix Q, "Weld Overlay Repair of Class 1,2, and 3 Austenitic Stainless Steel Piping Weldments," shall be met as part of the installation and inspection of the weld overlay. |
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| The NRC staff has reviewed the licensees submittal and determined that, in accordance with 10 CFR 50.55a(a)(3)(i), to perform a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the alternative proposed in Relief Request 1-ISI-22 is authorized for the second 10-year lSI interval at BFN, Unit 1 that is scheduled to end June 1, 2017. All other ASME Code, Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. | | ==3.0 TECHNICAL EVALUATION== |
| Principal Contributor: | | |
| G. Cheruvenki Date: August 24, 2009 P. Swafford -2 This relief is authorized for the remainder of the second 10-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1,2017. Docket No. | | 3.1 ASME Code Requirements for which Relief is Requested The lSI Code of record for BFN for the second 10-year lSI interval was the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. |
| Safety cc w/encl: Distribution via LPL2-2
| | Consistent with IWA-4220, repairs shall be performed in accordance with the licensee's design specification and the original Construction Code. Later editions and addenda of the Construction Code or of ASME Code, Section III, either in their entirety or portions thereof, and ASME Code Cases may be used. In this case, the licensee proposed to implement a weld overlay repair in accordance with ASME Code Case N-504-3 as modified by the condition placed on the code case in RG 1.147, Revision 15 and the approved alternatives. |
| | 3.2 Duration of Relief Request This relief request for Unit 1 is applicable to its second 1O-year lSI interval that is scheduled to end on June 1,2017. |
| | 3.3 Licensee's Proposed Alternative to ASME Code Case N-504-3 ASME Code Case N-504-3, Requirement (h) specifies that a hydrostatic test be performed in accordance with ASME Code, Section XI, IWA-5000 if the flaw penetrates the original pressure boundary. As an alternative, leak testing in accordance with IWA-5000 at nominal operating pressure and temperature in lieu of the system hydrostatic testing will be performed. |
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| | -3 3.4 Licensee's Justification for the Proposed Alternative Licensee stated in their justification for the granting of relief that, the stresses generated in the material during the system leak test at nominal operating pressure is less than 30 percent of the allowable stress and the stress generated by the hydrostatic pressure test was in the low 30-percent region of the allowable stress for that material. Material stress conditions in these ranges would not tend to drive flaw growth to such an extent that leakage would be generated or significantly increased. Therefore, no significant observable differences would be provided by the performance of the hydrostatic test and the system leakage test would provide an acceptable alternative. |
| | On this technical basis, hydrostatic test requirements were deleted from ASME Code Cases N-416, "Alternative Pressure Test Requirement for Welded or Brazed Joints for Replacement Parts and Piping Subassemblies, or Installation of Replacement Items by Welding or Brazing, Classes 1, 2, and 3 Section XI, Division 1," and N-498, "Alternative Requirements for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems Section XI, Division 1." The use of a system leak test at nominal operating pressure in lieu of a hydrostatic test has been incorporated in ASME Code, Section XI beginning in the 1998 Edition with the 1999 Addenda. Therefore, the licensee determined that this alternative provides an acceptable level of quality and safety. |
| | 3.5 Evaluation The licensee's proposed modification to Requirement (h) of ASME Code Case N-504-3 was to perform a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in accordance with ASME Code, Section XI (2001 Edition with the 2003 Addenda), |
| | IWA-5000 and, by reference, ASME Code, Section XI, IWB-5000. Precedence for use of a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in lieu of a hydrostatic test, which would be conducted at a higher pressure, has been set with ASME Code Case N-416-1. ASME Code Case N-416-1 was accepted by the NRC staff in RG 1.147 and has been incorporated into ASME Code, Section XI beginning in the 1998 Edition with the 1999 Addenda. Unit 1 is currently in its second 10-year lSI interval and the lSI Code of record for this interval is the ASME Code, Section XI, 2001 Edition, including 2003 Addenda. The NRC staff reviewed the licensee's justification for the proposed alternative and finds it acceptable based on the following: |
| | : 1. since similar stresses are produced in the material during a system leak test at the nominal operating pressure corresponding to 1OO-percent rated reactor power or during the hydrostatic test, any leakage that would otherwise occur during operation due to an existing defect will be identified regardless of the type of test (Le., hydrostatic test or system leak test) that is performed on the weld overlay, |
| | : 2. substitution of a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power for a hydrostatic test was incorporated in ASME Code, Section XI, 1998 Edition, 1999 Addenda, and |
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| | : 3. TVA, the licensee's alternative is consistent with the current industry practice, and a similar request by the license holder for the Cooper Nuclear Station was approved by the NRC staff in its letter dated August 15, 2008. |
| | Based on the above, the NRC staff determined that TVA, the licensee's proposed alternative to perform a system leak test at the nominal operating pressure corresponding to 1OO-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety. |
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| | ==4.0 CONCLUSION== |
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| | The NRC staff has reviewed the licensees submittal and determined that, in accordance with 10 CFR 50.55a(a)(3)(i), to perform a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the alternative proposed in Relief Request 1-ISI-22 is authorized for the second 10-year lSI interval at BFN, Unit 1 that is scheduled to end June 1, 2017. |
| | All other ASME Code, Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: G. Cheruvenki Date: August 24, 2009 |
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| | P. Swafford -2 This relief is authorized for the remainder of the second 10-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1,2017. |
| | Sincerely, IRA! |
| | Thomas H. Boyce, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259 |
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| | ==Enclosure:== |
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| DDiaz-Toro, ADAMS ACCESSION No*.. | | Safety Evaluation cc w/encl: Distribution via Listserv Distribution: |
| Sincerely, IRA! Thomas H. Boyce, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation NRR-106 OFFICE LPL2-1/PM LPL2-2/PM LPLP-WB/LA CVIB/BC LPL2-2/BC NAME VSreenivas SLingam for EBrown BClayton MMitchell by memo TBoyce DATE 8/12/09 08/19/09 08/20109 02/9109 08/24/09 OFFICIAL RECORD COPY}}
| | PUBLIC LPL2-2 RtF RidsNrrPMBrownsFerry RidsNrrDorlLpl2-2 RidsAcrsAcnw_MailCenter RidsNrrDciCvib RidsOgcRp RidsNrrLABClayton GCheruvenki DDiaz-Toro, EDO RidsRgn2MailCenter VSreenivas ADAMS ACCESSION No*.. ML092180954 NRR-106 OFFICE LPL2-1/PM LPL2-2/PM LPLP-WB/LA CVIB/BC LPL2-2/BC NAME VSreenivas SLingam for BClayton MMitchell by TBoyce EBrown memo DATE 8/12/09 08/19/09 08/20109 02/9109 08/24/09 OFFICIAL RECORD COPY}} |
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MONTHYEARML0833802012008-11-25025 November 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Second Ten-year Inspection Interval - Relief Request for 1-ISI-22 Project stage: Request ML0921809542009-08-24024 August 2009 Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 Project stage: Other 2008-11-25
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Category:Code Relief or Alternative
MONTHYEARML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22329A0762022-12-0101 December 2022 Correction of Error in Authorization of Alternative Request BFN-21-ISI-02 ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17135A1462017-08-18018 August 2017 Browns Ferry Nuclear Plant, Unit 3 - Relief Request No. 3 ISI 29 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Piping Welds (CAC No. MF9258) ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17045A7722017-03-14014 March 2017 Browns Ferry Nuclear Plant, Units 2 and 3 - Relief Request 2-ISI-30 and 3-ISI-27 - Relief from ASME Code, Section XI Requirements for Periods of Extended Operation for RPV Circumferential Shell Weld Examinations (CAC Nos. MF7795 and MF7796) ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16020A1152016-02-17017 February 2016 Alternative Relief Request 1-ISI-27 for Relief from the Reactor Vessel Circumferential Weld Examination Requirements of the ASME Code ML12003A0812012-01-20020 January 2012 Safety Evaluation for Relief Request 3-ISI-25, for the Third 10-Year Inservice Inspection Interval ML0921809542009-08-24024 August 2009 Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 ML0916703582009-07-0101 July 2009 Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ML0912000402009-06-16016 June 2009 Safety Evaluation for Relief Request 2-ISI-18R1 Associated with Inservice Inspection Examination Coverage ML0916104992009-06-12012 June 2009 Verbal Relief Related to Instrument Line Weld Overlay (TAC No. ME1319) (2-ISI-21) ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0907110772009-04-0202 April 2009 Safety Evaluation for Relief Request 1-ISI-18 Associated with Inspection and Testing of Snubbers ML0833802012008-11-25025 November 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Second Ten-year Inspection Interval - Relief Request for 1-ISI-22 ML0821704212008-07-29029 July 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval- Request for Relief 2-ISI-18, Revision 1 ML0800805242008-05-20020 May 2008 Safety Evaluation for Relief Request 3-ISI-22 Limited Examination Coverage for Valve to Pipe Weld GR-3-63 Tac No. MD6748) ML0725600472007-08-24024 August 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval Requests for Relief 3-ISI-22 & 3-ISI-23 ML0706504752007-02-21021 February 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Second Ten-Year Inspection Interval - Request for Relief 3-ISI-7, Revision 2 ML0700903492007-02-12012 February 2007 Relief Request, Risk-Informed Inservice Inspection of Piping ML0633306482006-12-22022 December 2006 Relief Request, Request for Relief from American Society of Mechanical Engineers, Section XI Requirements for the Third Inservice Inspection Interval - Snubbers ML0631800372006-11-14014 November 2006 Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification ML0615600902006-08-0303 August 2006 Relief Requests, Revision 3-ISI-12 and 3-ISI-19, Associated with Weld Examination Coverage ML0615902822006-07-0303 July 2006 Letter Withdrawal of Relief Requests Regarding Third Interval Inservice Inspection Requirements of the ASME Code ML0613903032006-06-30030 June 2006 Relief, Relief Request 3-ISI-20 Associated with the Use of ASME Code Case- 700 for the Third Inservice Inspection Interval ML0535403782005-12-20020 December 2005 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request to Use Subsequent Edition and Addenda of ASME Section XI Code for Repair and Replacement Activities ML0523101262005-08-18018 August 2005 American Society of Mechanical Engineers RPV Welds Withdrawal of Requests ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0518106792005-07-18018 July 2005 Safety Evaluation for Request for Relief Regarding the Use of ASME Code Case 700 (TACs MC6437, MC6438) ML0506305582005-03-0404 March 2005 American Society of Mechanical Engineers Section XI, Inservice Inspection Program, Second Ten-Year Inspection Interval - Requests for Relief 3-ISI-7, Revision 1, 3-ISI-12, and 3-ISI-19 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0433803212004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, in Service Inspection Program ML0432206272004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Requests for Relief 2-ISI-22, and 3-ISI-18 for Examination of Reactor Pressure Vessel Nozzle-To-Vessel Shell Welds and Nozze Blend. ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0410403752004-04-12012 April 2004 Requests for Relief Nos. 2-ISI-18 and 2-ISI-19 for Third 10-Year Interval Inservice Inspection ML0406200482004-03-0101 March 2004 Brown Ferry, Unit 1, Ltr, Relief, Containment Inservice Inspection ML0404203552004-02-11011 February 2004 Relief, Second 10-Year Interval Inservice Inspection Programs ML0335303822003-12-19019 December 2003 Brown Ferry Nuclear Plant, Units 2 and 3, Relief Request, 2-ISI-21 and 3-ISI-17 to Inservice Inspection Program ML0325909292003-09-12012 September 2003 (BFN) - Unit 1 - American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief PDI-2 - Clarification and Additional Information ML0316714662003-06-0202 June 2003 Relief, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval - Requests for Relief 2-ISI-18, and 2-ISI-19 ML0314107352003-05-0909 May 2003 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3 -ISI-14, & 3-ISI-15 ML0313500882003-05-0909 May 2003 (Bfn), Unit 3, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3-ISI-14 & 3-ISI-15 2024-06-18
[Table view] Category:Letter
MONTHYEARML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24106A2612024-04-16016 April 2024 Ltr to State Recognized Tribes-Everhart, Piqua Shawnee Tribe ML24106A2452024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Cernek, Couchatta Tribe of Louisiana ML24106A2472024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hicks, Eastern Band of Cherokee Indians ML24106A2632024-04-16016 April 2024 Ltr to State Recognized Tribes-Hamilton, Cher-O-Creek Intra Tribal Indians ML24106A2512024-04-16016 April 2024 Letter to Federally Recognized Tribes-Morrow, Thlopthlocco Tribal Town ML24102A0392024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Johnson, Absentee Tribe of Shawnee ML24106A2462024-04-16016 April 2024 Letter to Federally Recognized Tribes-Cypress, Miccosukee Tribe ML24106A2482024-04-16016 April 2024 Letter to Federally Recognized Tribes-Hill, Muscogee (Creek) Nation ML24106A2402024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Barnes, Shawnee Tribe 2024-09-03
[Table view] Category:Safety Evaluation
MONTHYEARML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20253A1812020-09-23023 September 2020 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Code ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times ML19329E3192020-01-0202 January 2020 SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044) ML19294A0112019-12-26026 December 2019 Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19198A0012019-08-13013 August 2019 Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140) ML19037A1372019-04-0202 April 2019 Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML19016A2152019-02-28028 February 2019 Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-46 ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML18241A3192018-10-0909 October 2018 Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML18236A3312018-09-24024 September 2018 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) ML17032A1202017-08-14014 August 2017 Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... 2024-01-03
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: BROWNS FERRY NUCLEAR PLANT-UNIT 1, THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM RELATED TO ASME CODE CASE N-504-3, ALTERNATIVE RULES FOR REPAIR OF CLASSES 1,2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME0155)
Dear Mr. Swafford:
By letter dated November 25,2008, the Tennessee Valley Authority (TVA, the licensee) submitted Relief Request (RR) 1-ISI-22 requesting relief'from the requirements specified in the American Society of Mechanical Engineers (ASME) Code,Section XI for repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping weld overlays under Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i) for the Browns Ferry Nuclear Plant (BFN), Unit 1. The request proposed that in lieu of the requirements of the ASME Code, Case N-504-3, Paragraph (h),
performing a system hydrostatic test, proposed an alternative to perform a system leakage test at normal operating pressure and temperature.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided in TVA's November 25,2008, letter. The NRC staff concluded that the proposed alternative described in the licensee's letter provides an acceptable level of quality and safety.
Therefore, RR-1-ISI-22 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Browns Ferry Nuclear Plant, Unit 1. All other requirements of the ASME Code,Section XI for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
P. Swafford -2 This relief is authorized for the remainder of the second 1O-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1, 2017.
Sincerely, Docket No. 50-259
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST 1-ISI-22 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259
1.0 INTRODUCTION
By letter dated November 25, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083380201), the Tennessee Valley Authority (TVA, the licensee),
requested relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) requirements at Browns Ferry Nuclear Plant, Unit 1 (BFN).
As an alternative to the ASME Code requirements, TVA proposed to implement a full structural weld overlay (FSWOL) repair in accordance with ASME Code Case N-504-3, Alternative Rules for Repair of Class 1, 2, and 3, "Austenitic Stainless Steel Piping,Section XI, Division 1," as modified by TVA in its submitlalletters. The alternative documented in Relief Request (RR) 1-ISI-22 would be used to perform a leak test in lieu of a hydrostatic test on the FSWOL applied to the reactor pressure vessel (RPV) Feedwater N-1'1 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld.
Although, the licensee has already implemented the installation of the FSWOL prior to the issuance of this safety evaluation (SE), this SE is being issued to document the decision made by the U.S. Nuclear Regulatory Commission (NRC) staff to grant the licensee's request by verbal authorization on November 26,2008. The NRC staff's memorandum dated December 12,2008 (ADAMS Accession No. ML083390526), reflects the basis for verbal approval.
2.0 REGULATORY EVALUATION
Pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supportS) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection (lSI) of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the "first ten-year lSI interval and subsequent intervals comply Enclosure
-2 with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. BFN, Unit 1 second 1O-year lSI interval is scheduled to end on June 1, 2017. The lSI Code of record for BFN for the second 10-year lSI interval is the ASME Code,Section XI, 2001 Edition, including 2003 Addenda.
Pursuant to 10 CFR 50.55a(a)(3), alternatives to requirements may be authorized if the licensee demonstrates that: (i) the proposed alternatives provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. TVA, submitted the subject relief request, pursuant to 10 CFR 50.55a(a)(3)(i), which proposed an alternative to the implementation of the ASME Code,Section XI requirements based on ASME Code Case N-504-3, the deposition of a FSWOL for the remaining service life of the identified components.
ASME Code Case N-504-3 was conditionally accepted by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,"
issued in October 2007. In RG 1.147, Revision 15, the NRC accepted ASME Code Case N-504-3 with the condition that the inspection requirements of ASME Code,Section XI, Nonmandatory Appendix Q, "Weld Overlay Repair of Class 1,2, and 3 Austenitic Stainless Steel Piping Weldments," shall be met as part of the installation and inspection of the weld overlay.
3.0 TECHNICAL EVALUATION
3.1 ASME Code Requirements for which Relief is Requested The lSI Code of record for BFN for the second 10-year lSI interval was the ASME Code,Section XI, 2001 Edition, including 2003 Addenda.
Consistent with IWA-4220, repairs shall be performed in accordance with the licensee's design specification and the original Construction Code. Later editions and addenda of the Construction Code or of ASME Code,Section III, either in their entirety or portions thereof, and ASME Code Cases may be used. In this case, the licensee proposed to implement a weld overlay repair in accordance with ASME Code Case N-504-3 as modified by the condition placed on the code case in RG 1.147, Revision 15 and the approved alternatives.
3.2 Duration of Relief Request This relief request for Unit 1 is applicable to its second 1O-year lSI interval that is scheduled to end on June 1,2017.
3.3 Licensee's Proposed Alternative to ASME Code Case N-504-3 ASME Code Case N-504-3, Requirement (h) specifies that a hydrostatic test be performed in accordance with ASME Code,Section XI, IWA-5000 if the flaw penetrates the original pressure boundary. As an alternative, leak testing in accordance with IWA-5000 at nominal operating pressure and temperature in lieu of the system hydrostatic testing will be performed.
-3 3.4 Licensee's Justification for the Proposed Alternative Licensee stated in their justification for the granting of relief that, the stresses generated in the material during the system leak test at nominal operating pressure is less than 30 percent of the allowable stress and the stress generated by the hydrostatic pressure test was in the low 30-percent region of the allowable stress for that material. Material stress conditions in these ranges would not tend to drive flaw growth to such an extent that leakage would be generated or significantly increased. Therefore, no significant observable differences would be provided by the performance of the hydrostatic test and the system leakage test would provide an acceptable alternative.
On this technical basis, hydrostatic test requirements were deleted from ASME Code Cases N-416, "Alternative Pressure Test Requirement for Welded or Brazed Joints for Replacement Parts and Piping Subassemblies, or Installation of Replacement Items by Welding or Brazing, Classes 1, 2, and 3 Section XI, Division 1," and N-498, "Alternative Requirements for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 SystemsSection XI, Division 1." The use of a system leak test at nominal operating pressure in lieu of a hydrostatic test has been incorporated in ASME Code,Section XI beginning in the 1998 Edition with the 1999 Addenda. Therefore, the licensee determined that this alternative provides an acceptable level of quality and safety.
3.5 Evaluation The licensee's proposed modification to Requirement (h) of ASME Code Case N-504-3 was to perform a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in accordance with ASME Code,Section XI (2001 Edition with the 2003 Addenda),
IWA-5000 and, by reference, ASME Code,Section XI, IWB-5000. Precedence for use of a system leak test at the nominal operating pressure corresponding to 100 percent rated reactor power in lieu of a hydrostatic test, which would be conducted at a higher pressure, has been set with ASME Code Case N-416-1. ASME Code Case N-416-1 was accepted by the NRC staff in RG 1.147 and has been incorporated into ASME Code,Section XI beginning in the 1998 Edition with the 1999 Addenda. Unit 1 is currently in its second 10-year lSI interval and the lSI Code of record for this interval is the ASME Code,Section XI, 2001 Edition, including 2003 Addenda. The NRC staff reviewed the licensee's justification for the proposed alternative and finds it acceptable based on the following:
- 1. since similar stresses are produced in the material during a system leak test at the nominal operating pressure corresponding to 1OO-percent rated reactor power or during the hydrostatic test, any leakage that would otherwise occur during operation due to an existing defect will be identified regardless of the type of test (Le., hydrostatic test or system leak test) that is performed on the weld overlay,
- 2. substitution of a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power for a hydrostatic test was incorporated in ASME Code,Section XI, 1998 Edition, 1999 Addenda, and
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- 3. TVA, the licensee's alternative is consistent with the current industry practice, and a similar request by the license holder for the Cooper Nuclear Station was approved by the NRC staff in its letter dated August 15, 2008.
Based on the above, the NRC staff determined that TVA, the licensee's proposed alternative to perform a system leak test at the nominal operating pressure corresponding to 1OO-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety.
4.0 CONCLUSION
The NRC staff has reviewed the licensees submittal and determined that, in accordance with 10 CFR 50.55a(a)(3)(i), to perform a system leak test at the nominal operating pressure corresponding to 100-percent rated reactor power on the FSWOL applied to the Feedwater N-11 B-1 austenitic stainless steel process pipe-to-austenitic stainless steel safe end weld in lieu of a hydrostatic test provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the alternative proposed in Relief Request 1-ISI-22 is authorized for the second 10-year lSI interval at BFN, Unit 1 that is scheduled to end June 1, 2017.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: G. Cheruvenki Date: August 24, 2009
P. Swafford -2 This relief is authorized for the remainder of the second 10-year inservice inspection interval at BFN, Unit 1 that is scheduled to end June 1,2017.
Sincerely, IRA!
Thomas H. Boyce, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
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