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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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| =Text= | | =Text= |
| {{#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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| | -4 |
| | : 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}} |
Letter Sequence Other |
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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
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML23159A2552023-07-20020 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
ML0230202092002-10-25025 October 2002
(Bfn), Unit 2, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Request for Relief 2-ISI-13, Examination & Testing of Snubbers
2023-07-20
[Table view]
Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024
Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
ML24023A2802024-01-23023 January 2024
Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump
CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions
ML24016A3042024-01-16016 January 2024
Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024
Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47
ML24022A1732024-01-0303 January 2024
Receipt and Availability of the Subsequent License Renewal Application
ML23319A1992024-01-0303 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
ML23355A2062023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23348A3942023-12-14014 December 2023
Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
IR 05000259/20230102023-12-11011 December 2023
Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010
ML23335A0722023-12-0101 December 2023
Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump
ML23334A2492023-11-30030 November 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023
Submittal of Fifth 10-Year Interval Inservice Testing Program Plan
ML23331A2532023-11-27027 November 2023
Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML23325A1102023-11-21021 November 2023
Anchor Darling Double Disc Gate Valve Commitment Revision
ML23320A2542023-11-16016 November 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
IR 05000259/20230032023-11-13013 November 2023
Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003
IR 05000259/20230402023-11-0202 November 2023
Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter
ML23292A2532023-10-18018 October 2023
BFN 2024-301, Corporate Notification Letter (210-day Ltr)
ML23282A0022023-10-0606 October 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
ML23278A0122023-10-0505 October 2023
Updated Final Safety Analysis Report, Amendment 30
ML23271A1702023-09-28028 September 2023
Site Emergency Plan Implementing Procedure Revision
ML23270A0702023-09-26026 September 2023
SLRA Pre-Application Meeting Summary 09-13-2023
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision
ML23263B1042023-09-20020 September 2023
Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
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
CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64
IR 05000259/20230052023-08-29029 August 2023
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005
ML23233A0432023-08-18018 August 2023
Enforcement Action EA-22-122 Inspection Readiness Notification
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
ML23228A1642023-08-16016 August 2023
Site Emergency Plan Implementing Procedure Revision
ML23228A0202023-08-15015 August 2023
(BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
IR 05000259/20230022023-08-10010 August 2023
Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001
ML23192A4472023-07-31031 July 2023
Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023
Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills
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
ML23201A2182023-07-20020 July 2023
Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299)
ML23159A2552023-07-20020 July 2023
Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles
ML23199A3072023-07-18018 July 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023
Tennessee Valley Authority - Radiological Emergency Plan Revisions
IR 05000259/20233012023-07-18018 July 2023
NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301
2024-02-01
[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] |
Text
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:
Safety Evaluation cc w/encl: Distribution via Listserv Distribution:
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