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| | author name = Raghavan L | | | author name = Raghavan L |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Singer K W | | | addressee name = Singer K |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259 | | | docket = 05000259 |
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| {{#Wiki_filter:February 7, 2007Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:February 7, 2007 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT, UNIT 1 - RE: REQUEST FOR RELIEFFROM THE REQUIREMENTS OF THE ASME CODE (TAC NO. MD2681) | | BROWNS FERRY NUCLEAR PLANT, UNIT 1 - RE: REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE ASME CODE (TAC NO. MD2681) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| By letter dated July 12, 2006, the Tennessee Valley Authority (TVA) submitted a request forrelief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI at Browns Ferry Nuclear Plant, Unit 1. | | By letter dated July 12, 2006, the Tennessee Valley Authority (TVA) submitted a request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI at Browns Ferry Nuclear Plant, Unit 1. |
| Specifically, TVA requested relief from ASME Code inservice inspections (ISI) requirements forthree reactor pressure vessel longitudinal shell welds as the examination requirement of essentially 100 percent coverage is impractical due to permanently installed piping that restricts access to the examination areas.The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated theinformation provided in support of TVA's Relief Request 1-ISI-21, related to the first 10-year interval ISI requirements. Based on the conclusions contained in the enclosed safety evaluation, the NRC staff agrees that the ASME Code requirements are impractical and grants relief pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(6)(i) on thebasis that the inservice examination of the reactor pressure vessel welds to the maximum extent possible provides a reasonable assurance of structural integrity.The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) isauthorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, relief is granted for the above requested first 10-year interval inspection pursuant to 10 CFR 50.55a(g)(6)(i).Sincerely,/RA Patrick D. Milano for/L. Raghavan, ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-259 | | Specifically, TVA requested relief from ASME Code inservice inspections (ISI) requirements for three reactor pressure vessel longitudinal shell welds as the examination requirement of essentially 100 percent coverage is impractical due to permanently installed piping that restricts access to the examination areas. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided in support of TVAs Relief Request 1-ISI-21, related to the first 10-year interval ISI requirements. Based on the conclusions contained in the enclosed safety evaluation, the NRC staff agrees that the ASME Code requirements are impractical and grants relief pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(6)(i) on the basis that the inservice examination of the reactor pressure vessel welds to the maximum extent possible provides a reasonable assurance of structural integrity. |
| | The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, relief is granted for the above requested first 10-year interval inspection pursuant to 10 CFR 50.55a(g)(6)(i). |
| | Sincerely, |
| | /RA Patrick D. Milano for/ |
| | L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next page | | Safety Evaluation cc w/encl: See next page |
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| ML063540620 NRR-028OFFICELPL2-2/PMLPL2-2/PMLPL2-2/LAOGCCVIB/BCLPL2-2/BCNAMELRegnerMChernoffBClaytonMBarkman NLOMMitchell by Memo datedPMilano forLRaghavanDATE02/07/07 02/07/07 02/07/06 02/05/0709/26/0602/07/07 EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONAMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XIFIRST 10-YEAR INSERVICE INSPECTION OF REACTOR VESSEL WELDSREQUEST FOR RELIEF 1-ISI-21TENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT UNIT 1DOCKET NO. 50-25 | | ML063540620 NRR-028 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA OGC CVIB/BC LPL2-2/BC NAME LRegner MChernoff BClayton MBarkman MMitchell PMilano for NLO by Memo dated LRaghavan DATE 02/07/07 02/07/07 02/07/06 02/05/07 09/26/06 02/07/07 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XI FIRST 10-YEAR INSERVICE INSPECTION OF REACTOR VESSEL WELDS REQUEST FOR RELIEF 1-ISI-21 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 1 DOCKET NO. 50-259 |
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| ==91.0INTRODUCTION== | | ==1.0 INTRODUCTION== |
| In accordance with Section 50.55a(g)(6)(ii)(A)(2) of Part 50 to Title 10 of the Code of FederalRegulations (CFR), the Tennessee Valley Authority (TVA, the licensee) has requested to satisfythe American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) inservice inspection (ISI) requirements with the examinations performed during the augmented reactor pressure vessel (RPV) circumferential and longitudinal shell weld examinations. Therefore, by letter dated July 12, 2006, the licensee submitted relief request (RR) 1-ISI-21 from certain ISI requirements in the ASME Code, Section XI, Rules forInservice Inspection of Nuclear Power Plant Components, for RPV longitudinal shell weldsV-3-A, V-3-B, and V-3-C for Unit 1. 2.0REGULATORY REQUIREMENTSThe ISI requirements of ASME Code Class 1, 2, and 3 components are performed inaccordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). In accordance with 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components shall meetthe requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that the ISI of components and system pressure tests conducted duringthe first 10-year interval and subsequent intervals comply 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. The ASME Code of record for the Unit 1 first interval 10-year ISI program is the 1995 Edition through the 1996 Addenda of Section XI of theASME Code.
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| ==3.0TECHNICAL EVALUATION==
| | In accordance with Section 50.55a(g)(6)(ii)(A)(2) of Part 50 to Title 10 of the Code of Federal Regulations (CFR), the Tennessee Valley Authority (TVA, the licensee) has requested to satisfy the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) inservice inspection (ISI) requirements with the examinations performed during the augmented reactor pressure vessel (RPV) circumferential and longitudinal shell weld examinations. Therefore, by letter dated July 12, 2006, the licensee submitted relief request (RR) 1-ISI-21 from certain ISI requirements in the ASME Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C for Unit 1. |
| 3.1BackgroundBy letter dated March 15, 2006, TVA submitted RR 1-ISI-20 in accordance with 10 CFR50.55a(g)(6)(ii)(A) for augmented volumetric examinations of the Unit 1 RPV shell welds when essentially 100 percent of the weld examinations was not obtained. This RR contained an alternative to the examinations for welds V-3-A, V-3-B, and V-3-C. The licensee's alternative was authorized pursuant to 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(g)(6)(ii)(A)(5) by the NRC staff in a safety evaluation dated August 23, 2006 (Agencywide Documents Access and Management System Accession No. ML060960040) as it provided an acceptable level of quality and safety.3.2Components for Which Relief is RequestedThe affected component is the Unit 1 RPV; specifically, the welds identified in the table below. The examination category and item number are from the ASME Code, Section XI, Table IWB-500-1.Examination CategoryItem NumberDescriptionWeld Nos.B-AB1.12RPV Longitudinal ShellWeldsV-3-A, V-3-B, V-3-C3.3ASME Code RequirementsASME Code, Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.12,requires volumetric examination of essentially 100 percent of the weld length of all longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds
| | 2.0 REGULATORY REQUIREMENTS The ISI requirements of ASME Code Class 1, 2, and 3 components are performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). |
| ,approved for use by the NRC staff in Regulatory Guide (RG) 1.147, Revision 14, InserviceInspection Code Case Acceptability (RG 1.147), states that a reduction in examinationcoverage due to part geometry or interference for any Class 1 and 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained).3.4Basis for ReliefIn accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has requested relief from certain ISIweld examination requirements specified in Section XI of the ASME Code for the Unit 1 RPV under RR 1-ISI-21.TVA has determined that 3 of the 15 longitudinal shell welds in the RPV have nondestructiveexamination coverage limitations (less than 90 percent coverage completed), which exceeds that specified in Table IWB-2500-1 of Section XI of the ASME Code. The licensee states thatcompliance with the extent of the examination which requires "essentially 100 percent" of the weld length is impractical and will result in unusual difficulty and unnecessary radiation exposure to various plant personnel without any compensating increase in the level of quality or safety. TVA states that areas of the V-3-A, V-3-B, and V-3-C welds were inaccessible for ultrasonicexamination due to the design configuration of the RPV and vessel internals. The examinations were performed with automated ultrasonic equipment from the vessel inside surface; however, portions of the shell weld scans were obstructed by core spray piping and feedwater spargers. | | In accordance with 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code to the extent practical within the limitations of design, geometry, and materials of construction of the components. |
| TVA also stated that conducting ultrasonic examination of these subject welds from the outside surfaces is not practical because of inaccessibility due to RPV outside insulation design and the proximity to the biological shield wall. In lieu of the ASME Code-required essentially 100-percent volume coverage using ultrasonicexamination, TVA performed an ultrasonic examination of accessible areas to the maximumextent practical given the component design and configuration of the subject RPV welds for Unit 1.Volumetric Coverage ObtainedWeld No.Percent CoverageExaminationLimitationV-3-A77.7Core Spray Piping andFeedwater SpargersV-3-B77.4Core Spray Piping andFeedwater SpargersV-3-C77.6Core Spray Piping andFeedwater Spargers4.0STAFF EVALUATIONThe ASME Code requires volumetric examination of essentially 100 percent of the weld lengthof all RPV longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2. The licensee proposed that the ultrasonic examinations performed during the augmented RPV shell weld examination of accessible areas to the maximum extent practical be accepted in lieu of the ASME Code requirements for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C. For RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, the staff determined that, based ondrawings provided and the licensee's basis for relief, complete ASME Code examination is impractical due to core spray piping and the feedwater spargers that restrict access to the examination areas. To perform the required ASME Code examination, the RPV and associated components would require design modifications. The licensee considered examining the subject welds from the outside of the RPV; however, it was not possible due to the insulation design and biological shield wall. Therefore, the staff determined that the ASME Code-requiredinspections are impractical and imposition of this requirement would cause a burden on the licensee without a compensating increase in the level of quality and safety.For welds V-3-A, V-3-B, and V-3-C the licensee obtained 77.7 percent, 77.4 percent, and77.6 percent volumetric coverage, respectively. The licensee obtained essentially 100 percent volumetric coverage on the twelve other RPV longitudinal shell welds. The coverage obtained for welds V-3-A, V-3-B, and V-3-C by the licensee represents a significant portion of the ASME Code-required weld length. The staff determined that these examinations and the examinations on the other 12 RPV longitudinal shell welds would have detected significant patterns of degradation, if any had occurred. The staff also determined that the examinations performed on welds V-3-A, V-3-B, and V-3-C and the 12 other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject welds.
| | The regulations require that the ISI of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply 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. The ASME Code of record for the Unit 1 first Enclosure |
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| ==5.0CONCLUSION== | | interval 10-year ISI program is the 1995 Edition through the 1996 Addenda of Section XI of the ASME Code. |
| For RR 1-ISI-21, the NRC staff concludes that the ASME Code-required examinations of RPVlongitudinal shell welds V-3-A, V-3-B, and V-3-C are impractical to perform due to physical obstructions and that imposition of this requirement would cause a burden on the licensee. The volumetric examinations performed to the extent practical on welds V-3-A, V-3-B, and V-3-C and the twelve other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject RPV welds. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), | | |
| relief is granted from the ASME Code ISI requirements of essentially 100 percent coverage for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, for the first 10-year ISI program at Unit 1.The staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorizedby law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. All other requirements of the ASME Code, Section XI for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.Principal contributors: Atif A. Shaikh Mr. Karl W. SingerBROWNS FERRY NUCLEAR PLANTTennessee Valley Authority cc: | | ==3.0 TECHNICAL EVALUATION== |
| Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Brian O'Grady, Site Vice PresidentBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Preston D. Swafford, Senior Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 General CounselTennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902Mr. John C. Fornicola, General ManagerNuclear Assurance Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Bruce Aukland, Plant ManagerBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Masoud Bajestani, Vice PresidentBrowns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Robert G. Jones, General ManagerBrowns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Larry S. MellenBrowns Ferry Unit 1 Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW. | | |
| Suite 23T85 Atlanta, GA 30303-8931 Ms. Beth A. Wetzel, ManagerCorporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. William D. Crouch, ManagerLicensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Senior Resident InspectorU.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970State Health OfficerAlabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017ChairmanLimestone County Commission 310 West Washington Street Athens, AL 35611Mr. Robert H. Bryan, Jr., General ManagerLicensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801}} | | 3.1 Background By letter dated March 15, 2006, TVA submitted RR 1-ISI-20 in accordance with 10 CFR 50.55a(g)(6)(ii)(A) for augmented volumetric examinations of the Unit 1 RPV shell welds when essentially 100 percent of the weld examinations was not obtained. This RR contained an alternative to the examinations for welds V-3-A, V-3-B, and V-3-C. The licensees alternative was authorized pursuant to 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(g)(6)(ii)(A)(5) by the NRC staff in a safety evaluation dated August 23, 2006 (Agencywide Documents Access and Management System Accession No. ML060960040) as it provided an acceptable level of quality and safety. |
| | 3.2 Components for Which Relief is Requested The affected component is the Unit 1 RPV; specifically, the welds identified in the table below. |
| | The examination category and item number are from the ASME Code, Section XI, Table IWB-500-1. |
| | Examination Category Item Number Description Weld Nos. |
| | B-A B1.12 RPV Longitudinal Shell V-3-A, V-3-B, V-3-C Welds 3.3 ASME Code Requirements ASME Code, Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.12, requires volumetric examination of essentially 100 percent of the weld length of all longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2. |
| | ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, approved for use by the NRC staff in Regulatory Guide (RG) 1.147, Revision 14, Inservice Inspection Code Case Acceptability (RG 1.147), states that a reduction in examination coverage due to part geometry or interference for any Class 1 and 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained). |
| | 3.4 Basis for Relief In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has requested relief from certain ISI weld examination requirements specified in Section XI of the ASME Code for the Unit 1 RPV under RR 1-ISI-21. |
| | TVA has determined that 3 of the 15 longitudinal shell welds in the RPV have nondestructive examination coverage limitations (less than 90 percent coverage completed), which exceeds |
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| | that specified in Table IWB-2500-1 of Section XI of the ASME Code. The licensee states that compliance with the extent of the examination which requires essentially 100 percent of the weld length is impractical and will result in unusual difficulty and unnecessary radiation exposure to various plant personnel without any compensating increase in the level of quality or safety. |
| | TVA states that areas of the V-3-A, V-3-B, and V-3-C welds were inaccessible for ultrasonic examination due to the design configuration of the RPV and vessel internals. The examinations were performed with automated ultrasonic equipment from the vessel inside surface; however, portions of the shell weld scans were obstructed by core spray piping and feedwater spargers. |
| | TVA also stated that conducting ultrasonic examination of these subject welds from the outside surfaces is not practical because of inaccessibility due to RPV outside insulation design and the proximity to the biological shield wall. |
| | In lieu of the ASME Code-required essentially 100-percent volume coverage using ultrasonic examination, TVA performed an ultrasonic examination of accessible areas to the maximum extent practical given the component design and configuration of the subject RPV welds for Unit 1. |
| | Volumetric Coverage Obtained Weld No. Percent Coverage Examination Limitation V-3-A 77.7 Core Spray Piping and Feedwater Spargers V-3-B 77.4 Core Spray Piping and Feedwater Spargers V-3-C 77.6 Core Spray Piping and Feedwater Spargers 4.0 STAFF EVALUATION The ASME Code requires volumetric examination of essentially 100 percent of the weld length of all RPV longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2. The licensee proposed that the ultrasonic examinations performed during the augmented RPV shell weld examination of accessible areas to the maximum extent practical be accepted in lieu of the ASME Code requirements for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C. |
| | For RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, the staff determined that, based on drawings provided and the licensees basis for relief, complete ASME Code examination is impractical due to core spray piping and the feedwater spargers that restrict access to the examination areas. To perform the required ASME Code examination, the RPV and associated components would require design modifications. The licensee considered examining the subject welds from the outside of the RPV; however, it was not possible due to the insulation |
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| | design and biological shield wall. Therefore, the staff determined that the ASME Code-required inspections are impractical and imposition of this requirement would cause a burden on the licensee without a compensating increase in the level of quality and safety. |
| | For welds V-3-A, V-3-B, and V-3-C the licensee obtained 77.7 percent, 77.4 percent, and 77.6 percent volumetric coverage, respectively. The licensee obtained essentially 100 percent volumetric coverage on the twelve other RPV longitudinal shell welds. The coverage obtained for welds V-3-A, V-3-B, and V-3-C by the licensee represents a significant portion of the ASME Code-required weld length. The staff determined that these examinations and the examinations on the other 12 RPV longitudinal shell welds would have detected significant patterns of degradation, if any had occurred. The staff also determined that the examinations performed on welds V-3-A, V-3-B, and V-3-C and the 12 other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject welds. |
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| | ==5.0 CONCLUSION== |
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| | For RR 1-ISI-21, the NRC staff concludes that the ASME Code-required examinations of RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C are impractical to perform due to physical obstructions and that imposition of this requirement would cause a burden on the licensee. The volumetric examinations performed to the extent practical on welds V-3-A, V-3-B, and V-3-C and the twelve other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject RPV welds. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), |
| | relief is granted from the ASME Code ISI requirements of essentially 100 percent coverage for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, for the first 10-year ISI program at Unit 1. |
| | The staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. All other requirements of the ASME Code, Section XI for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. |
| | Principal contributors: Atif A. Shaikh |
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| | Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc: |
| | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW. |
| | Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Ms. Beth A. Wetzel, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Preston D. Swafford, Senior Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, General Manager 10833 Shaw Road Nuclear Assurance Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Mr. Robert H. Bryan, Jr., General Manager Tennessee Valley Authority Licensing and Industry Affairs P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801}} |
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Category:Letter
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Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions
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Anchor Darling Double Disc Gate Valve Commitment Revision
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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
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Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
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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
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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
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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
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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
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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:Proprietary Information Review
MONTHYEARML23045A1192023-02-15015 February 2023
Proprietary Determination Letter Enclosure - Browns Ferry Atrium 11 LAR Supp. 6
ML23009B7502023-02-15015 February 2023
Request for Withholding Information from Public Disclosure for Supplement 6 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel
ML23010A0932023-02-13013 February 2023
Request for Withholding Information from Public Disclosure for Supplement 7 to Browns Ferry License Amendment Request Transition to Atrium 11 Fuel
ML22297A2352023-01-10010 January 2023
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ML22276A1012022-10-25025 October 2022
Request for Withholding Information from Public Disclosure for Supplement 4 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel
ML22276A1002022-10-0404 October 2022
Request for Withholding Information from Public Disclosure for Supplement 3 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel
ML22157A3272022-06-13013 June 2022
Request for Withholding Information from Public Disclosure
ML22154A1292022-06-13013 June 2022
Request for Withholding Information from Public Disclosure
ML22125A2632022-06-0101 June 2022
Request for Withholding Information from Public Disclosure for Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel
ML19136A2782019-08-26026 August 2019
Request for Withholding Information from Public Disclosure
ML19136A2542019-08-26026 August 2019
Request for Withholding Information from Public Disclosure
ML19133A1192019-08-26026 August 2019
Request for Withholding Information from Public Disclosure
ML19136A0582019-08-26026 August 2019
Request for Withholding Information from Public Disclosure
ML19163A1652019-08-0505 August 2019
Request for Withholding Information from Public Disclosure
ML19163A0802019-07-22022 July 2019
Request for Withholding Information from Public Disclosure
ML19136A3282019-07-22022 July 2019
Request for Withholding Information from Public Disclosure
ML19136A1342019-07-22022 July 2019
Request for Additional Information from Public Disclosure
ML19008A1752019-01-15015 January 2019
Request for Withholding Information from Public Disclosure
ML16305A2142016-10-31031 October 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request For Withholding Information From Public Disclosure (CAC Nos. MF6741, MF6742, MF6743)
ML16292A7222016-10-26026 October 2016
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ML16270A3662016-10-26026 October 2016
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ML16224A1202016-09-26026 September 2016
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ML16209A3992016-08-16016 August 2016
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ML16211A4352016-08-16016 August 2016
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ML16217A4432016-08-16016 August 2016
Request for Withholding Information from Public Disclosure
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ML16130A6002016-07-0707 July 2016
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ML16125A4062016-07-0606 July 2016
Request for Withholding Information from Public Disclosure
ML16124B0062016-05-19019 May 2016
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ML16123A3352016-05-16016 May 2016
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ML16124B1062016-05-12012 May 2016
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ML16120A0722016-05-12012 May 2016
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ML16124A9322016-05-12012 May 2016
Request for Withholding Information from Public Disclosure
ML16027A1612016-02-0202 February 2016
Request for Withholding of Proprietary Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1
ML16027A2312016-02-0202 February 2016
Request for Withholding of Proprietary Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1
ML15345A0102015-12-22022 December 2015
Request for Withholding of Proprietary Information from Public Disclosure
ML15289A5392015-11-0909 November 2015
Request for Withholding of Proprietary Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 3
ML15289A5822015-11-0909 November 2015
Request for Withholding of Proprietary Information from Public Disclosure for Browns Ferry Plant, Unit 3
ML15281A1682015-11-0505 November 2015
Request for Withholding of Proprietary Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 3
ML15170A3162015-09-0404 September 2015
Request for Withholding of Proprietary Information from Public Disclosure
ML15044A4802015-03-16016 March 2015
Request for Withholding of Proprietary Information from Public Disclosure
ML15006A3602015-01-26026 January 2015
Request for Withholding of Proprietary Information from Public Disclosure
ML14352A2872015-01-0808 January 2015
Request for Withholding Information from Public Disclosure Regarding Tennessee Valley Authority Compensatory Measures That Revise the Pressure and Temperature Limits Curves
ML14099A1032014-04-30030 April 2014
Request for Withholding Information from Public Disclosure for Tennessee Valley Authority Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Technical Specifications 2.1.1.2 in Support.
ML14099A0842014-04-30030 April 2014
Request for Withholding Information from Public Disclosure for Response to Request for Additional Information on Technical Specification Change TS-478
ML13088A1202013-05-30030 May 2013
Request for Withholding Information from Public Disclosure for Tennessee Valley Authority Commitment Related to Core Plate Bolt Stress Analysis
ML13088A0962013-05-30030 May 2013
Request for Withholding Information from Public Disclosure for Tennessee Valley Authority Commitment Related to Core Plate Bolt Stress Analysis
2023-02-15
[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
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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
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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
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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
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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
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2024-01-03
[Table view] |
Text
February 7, 2007 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - RE: REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE ASME CODE (TAC NO. MD2681)
Dear Mr. Singer:
By letter dated July 12, 2006, the Tennessee Valley Authority (TVA) submitted a request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI at Browns Ferry Nuclear Plant, Unit 1.
Specifically, TVA requested relief from ASME Code inservice inspections (ISI) requirements for three reactor pressure vessel longitudinal shell welds as the examination requirement of essentially 100 percent coverage is impractical due to permanently installed piping that restricts access to the examination areas.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided in support of TVAs Relief Request 1-ISI-21, related to the first 10-year interval ISI requirements. Based on the conclusions contained in the enclosed safety evaluation, the NRC staff agrees that the ASME Code requirements are impractical and grants relief pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g)(6)(i) on the basis that the inservice examination of the reactor pressure vessel welds to the maximum extent possible provides a reasonable assurance of structural integrity.
The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, relief is granted for the above requested first 10-year interval inspection pursuant to 10 CFR 50.55a(g)(6)(i).
Sincerely,
/RA Patrick D. Milano for/
L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Safety Evaluation cc w/encl: See next page
ML063540620 NRR-028 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA OGC CVIB/BC LPL2-2/BC NAME LRegner MChernoff BClayton MBarkman MMitchell PMilano for NLO by Memo dated LRaghavan DATE 02/07/07 02/07/07 02/07/06 02/05/07 09/26/06 02/07/07 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XI FIRST 10-YEAR INSERVICE INSPECTION OF REACTOR VESSEL WELDS REQUEST FOR RELIEF 1-ISI-21 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 1 DOCKET NO. 50-259
1.0 INTRODUCTION
In accordance with Section 50.55a(g)(6)(ii)(A)(2) of Part 50 to Title 10 of the Code of Federal Regulations (CFR), the Tennessee Valley Authority (TVA, the licensee) has requested to satisfy the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) inservice inspection (ISI) requirements with the examinations performed during the augmented reactor pressure vessel (RPV) circumferential and longitudinal shell weld examinations. Therefore, by letter dated July 12, 2006, the licensee submitted relief request (RR) 1-ISI-21 from certain ISI requirements in the ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C for Unit 1.
2.0 REGULATORY REQUIREMENTS The ISI requirements of ASME Code Class 1, 2, and 3 components are performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i).
In accordance with 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations require that the ISI of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply 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. The ASME Code of record for the Unit 1 first Enclosure
interval 10-year ISI program is the 1995 Edition through the 1996 Addenda of Section XI of the ASME Code.
3.0 TECHNICAL EVALUATION
3.1 Background By letter dated March 15, 2006, TVA submitted RR 1-ISI-20 in accordance with 10 CFR 50.55a(g)(6)(ii)(A) for augmented volumetric examinations of the Unit 1 RPV shell welds when essentially 100 percent of the weld examinations was not obtained. This RR contained an alternative to the examinations for welds V-3-A, V-3-B, and V-3-C. The licensees alternative was authorized pursuant to 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(g)(6)(ii)(A)(5) by the NRC staff in a safety evaluation dated August 23, 2006 (Agencywide Documents Access and Management System Accession No. ML060960040) as it provided an acceptable level of quality and safety.
3.2 Components for Which Relief is Requested The affected component is the Unit 1 RPV; specifically, the welds identified in the table below.
The examination category and item number are from the ASME Code,Section XI, Table IWB-500-1.
Examination Category Item Number Description Weld Nos.
B-A B1.12 RPV Longitudinal Shell V-3-A, V-3-B, V-3-C Welds 3.3 ASME Code Requirements ASME Code,Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.12, requires volumetric examination of essentially 100 percent of the weld length of all longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2.
ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, approved for use by the NRC staff in Regulatory Guide (RG) 1.147, Revision 14, Inservice Inspection Code Case Acceptability (RG 1.147), states that a reduction in examination coverage due to part geometry or interference for any Class 1 and 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained).
3.4 Basis for Relief In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has requested relief from certain ISI weld examination requirements specified in Section XI of the ASME Code for the Unit 1 RPV under RR 1-ISI-21.
TVA has determined that 3 of the 15 longitudinal shell welds in the RPV have nondestructive examination coverage limitations (less than 90 percent coverage completed), which exceeds
that specified in Table IWB-2500-1 of Section XI of the ASME Code. The licensee states that compliance with the extent of the examination which requires essentially 100 percent of the weld length is impractical and will result in unusual difficulty and unnecessary radiation exposure to various plant personnel without any compensating increase in the level of quality or safety.
TVA states that areas of the V-3-A, V-3-B, and V-3-C welds were inaccessible for ultrasonic examination due to the design configuration of the RPV and vessel internals. The examinations were performed with automated ultrasonic equipment from the vessel inside surface; however, portions of the shell weld scans were obstructed by core spray piping and feedwater spargers.
TVA also stated that conducting ultrasonic examination of these subject welds from the outside surfaces is not practical because of inaccessibility due to RPV outside insulation design and the proximity to the biological shield wall.
In lieu of the ASME Code-required essentially 100-percent volume coverage using ultrasonic examination, TVA performed an ultrasonic examination of accessible areas to the maximum extent practical given the component design and configuration of the subject RPV welds for Unit 1.
Volumetric Coverage Obtained Weld No. Percent Coverage Examination Limitation V-3-A 77.7 Core Spray Piping and Feedwater Spargers V-3-B 77.4 Core Spray Piping and Feedwater Spargers V-3-C 77.6 Core Spray Piping and Feedwater Spargers 4.0 STAFF EVALUATION The ASME Code requires volumetric examination of essentially 100 percent of the weld length of all RPV longitudinal shell welds in accordance with the examination requirements illustrated in Figure IWB-2500-2. The licensee proposed that the ultrasonic examinations performed during the augmented RPV shell weld examination of accessible areas to the maximum extent practical be accepted in lieu of the ASME Code requirements for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C.
For RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, the staff determined that, based on drawings provided and the licensees basis for relief, complete ASME Code examination is impractical due to core spray piping and the feedwater spargers that restrict access to the examination areas. To perform the required ASME Code examination, the RPV and associated components would require design modifications. The licensee considered examining the subject welds from the outside of the RPV; however, it was not possible due to the insulation
design and biological shield wall. Therefore, the staff determined that the ASME Code-required inspections are impractical and imposition of this requirement would cause a burden on the licensee without a compensating increase in the level of quality and safety.
For welds V-3-A, V-3-B, and V-3-C the licensee obtained 77.7 percent, 77.4 percent, and 77.6 percent volumetric coverage, respectively. The licensee obtained essentially 100 percent volumetric coverage on the twelve other RPV longitudinal shell welds. The coverage obtained for welds V-3-A, V-3-B, and V-3-C by the licensee represents a significant portion of the ASME Code-required weld length. The staff determined that these examinations and the examinations on the other 12 RPV longitudinal shell welds would have detected significant patterns of degradation, if any had occurred. The staff also determined that the examinations performed on welds V-3-A, V-3-B, and V-3-C and the 12 other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject welds.
5.0 CONCLUSION
For RR 1-ISI-21, the NRC staff concludes that the ASME Code-required examinations of RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C are impractical to perform due to physical obstructions and that imposition of this requirement would cause a burden on the licensee. The volumetric examinations performed to the extent practical on welds V-3-A, V-3-B, and V-3-C and the twelve other RPV longitudinal shell welds provide a reasonable assurance of the structural integrity of the subject RPV welds. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i),
relief is granted from the ASME Code ISI requirements of essentially 100 percent coverage for RPV longitudinal shell welds V-3-A, V-3-B, and V-3-C, for the first 10-year ISI program at Unit 1.
The staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal contributors: Atif A. Shaikh
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Ms. Beth A. Wetzel, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Preston D. Swafford, Senior Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, General Manager 10833 Shaw Road Nuclear Assurance Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Mr. Robert H. Bryan, Jr., General Manager Tennessee Valley Authority Licensing and Industry Affairs P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
