|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:January 18, 2007Mr. Charles D. NaslundSenior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251 | | {{#Wiki_filter:January 18, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| CALLAWAY PLANT, UNIT 1 - REQUEST FOR RELIEF NO. ISI-35 FORSECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3434) | | CALLAWAY PLANT, UNIT 1 - REQUEST FOR RELIEF NO. ISI-35 FOR SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3434) |
|
| |
|
| ==Dear Mr. Naslund:== | | ==Dear Mr. Naslund:== |
|
| |
|
| By letter dated October 25, 2006 (ULNRC-05183), the Union Electric Company (the licensee)requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs)ISI-34, ISI-35, ISI-36, ISI-37, SI-38, ISI-39, ISI-40, and ISI-41 were submitted in that letter. This letter addresses RR ISI-35.Based on the attached safety evaluation, the Nuclear Regulatory Commission (NRC) staff hasdetermined that the ASME Code examination coverage requirements are impractical for the subject weld listed in RR ISI-35, and that the proposed inspection provides reasonable assurance of structural integrity. Therefore, granting relief, pursuant to paragraph 50.55a(g)(6)(i) of Title 10 of the Code of Federal Regulations, is authorized by law and will notendanger 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, the NRC staff grants the relief in RR ISI-35 for the second 10-year ISI interval at Callaway. 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.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-483 | | By letter dated October 25, 2006 (ULNRC-05183), the Union Electric Company (the licensee) requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs) |
| | ISI-34, ISI-35, ISI-36, ISI-37, SI-38, ISI-39, ISI-40, and ISI-41 were submitted in that letter. This letter addresses RR ISI-35. |
| | Based on the attached safety evaluation, the Nuclear Regulatory Commission (NRC) staff has determined that the ASME Code examination coverage requirements are impractical for the subject weld listed in RR ISI-35, and that the proposed inspection provides reasonable assurance of structural integrity. Therefore, granting relief, pursuant to paragraph 50.55a(g)(6)(i) of Title 10 of the Code of Federal Regulations, 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, the NRC staff grants the relief in RR ISI-35 for the second 10-year ISI interval at Callaway. 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. |
| | Sincerely, |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl:See next page | | Safety Evaluation cc w/encl: See next page |
|
| |
|
| ML063520318OFFICENRR/LPL4/PMNRR/LPL4/LACVIB/BCOGC-NLO w/commentsNRR/LPL4/BCNAMEJDonohewLFeizollahiMMitchellJRundDTerao DATE12/21/0712/19/0712/12/061/2/071/18/07 June 2006Callaway Plant, Unit 1 cc:Professional Nuclear Consulting, Inc.
| | ML063520318 OFFICE NRR/LPL4/PM NRR/LPL4/LA CVIB/BC OGC-NLO w/comments NRR/LPL4/BC NAME JDonohew LFeizollahi MMitchell JRund DTerao DATE 12/21/07 12/19/07 12/12/06 1/2/07 1/18/07 |
| 19041 Raines Drive Derwood, MD 20855John O'Neill, Esq.Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street, N.W.
| |
| Washington, D.C. 20037Mr. Keith A. Mills, Supervising EngineerRegional Regulatory Affairs/Safety Analysis AmerenUE P.O. Box 620 Fulton, MO 65251U.S. Nuclear Regulatory CommissionResident Inspector Office
| |
|
| |
|
| 8201 NRC Road Steedman, MO 65077-1302Mr. Les H. KanuckelManager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251Missouri Public Service CommissionGovernor Office Building 200 Madison Street Jefferson City, MO 65102-0360Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Mr. H. Floyd GilzowDeputy Director for Policy Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176Mr. Rick A. MuenchPresident and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839Mr. Dan I. Bolef, PresidentKay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130Mr. Lee Fritz, Presiding CommissionerCallaway County Court House 10 East Fifth Street Fulton, MO 65151Mr. David E. Shafer Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 66149, MC 470 St. Louis, MO 63166-6149Manager, Regulatory AffairsAmerenUE P.O. Box 620 Fulton, MO 65251Mr. Keith G. Henke, PlannerDivision of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102Certrec Corporation4200 South Hulen, Suite 630 Fort Worth, TX 76109Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONSECOND 10-YEAR INTERVAL INSERVICE INSPECTIONREQUEST FOR RELIEF NO. ISI-35UNION ELECTRIC COMPANYCALLAWAY PLANT, UNIT 1DOCKET NO. 50-48
| | Callaway Plant, Unit 1 cc: |
| | Professional Nuclear Consulting, Inc. Mr. Dan I. Bolef, President 19041 Raines Drive Kay Drey, Representative Derwood, MD 20855 Board of Directors Coalition for the Environment John ONeill, Esq. 6267 Delmar Boulevard Pillsbury Winthrop Shaw Pittman LLP University City, MO 63130 2300 N. Street, N.W. |
| | Washington, D.C. 20037 Mr. Lee Fritz, Presiding Commissioner Callaway County Court House Mr. Keith A. Mills, Supervising Engineer 10 East Fifth Street Regional Regulatory Affairs/Safety Analysis Fulton, MO 65151 AmerenUE P.O. Box 620 Mr. David E. Shafer Fulton, MO 65251 Superintendent, Licensing Regulatory Affairs U.S. Nuclear Regulatory Commission AmerenUE Resident Inspector Office P.O. Box 66149, MC 470 8201 NRC Road St. Louis, MO 63166-6149 Steedman, MO 65077-1302 Manager, Regulatory Affairs Mr. Les H. Kanuckel AmerenUE Manager, Quality Assurance P.O. Box 620 AmerenUE Fulton, MO 65251 P.O. Box 620 Fulton, MO 65251 Mr. Keith G. Henke, Planner Division of Community and Public Health Missouri Public Service Commission Office of Emergency Coordination Governor Office Building 930 Wildwood P.O. Box 570 200 Madison Street Jefferson City, MO 65102 Jefferson City, MO 65102-0360 Certrec Corporation Regional Administrator, Region IV 4200 South Hulen, Suite 630 U.S. Nuclear Regulatory Commission Fort Worth, TX 76109 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Director, Missouri State Emergency Management Agency Mr. H. Floyd Gilzow P.O. Box 116 Deputy Director for Policy Jefferson City, MO 65102-0116 Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839 June 2006 |
|
| |
|
| ==31.0INTRODUCTION==
| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SECOND 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. ISI-35 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 |
| By application dated October 25, 2006 (Agencywide Documents Access and ManagementSystem Accession No. ML063050203), Union Electric Company (the licensee) requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs) ISI-34, ISI-35, ISI-36, ISI-37, ISI-38, ISI-39, ISI-40, and ISI-41 were submitted in the letter. This safety evaluation addresses RR ISI-35.2.0REGULATORY REQUIREMENTSISI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASMECode) Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code and applicable addenda as required by paragraph 50.55a(g) of Title 10 of the Code ofFederal Regulation (10 CFR). Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section XI, "Rules for Inservice Inspection 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 testsconducted 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) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. However, if a licensee determines that conformance with these requirements is impractical, it may request relief from these specific requirements. Pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant such relief and may impose alternative requirements as it determines 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 therequirements were imposed on the facility.The licensee stated that the ASME Code of record for the Callaway Plant second 10-yearinterval inservice inspection program is the 1989 Edition with no Addenda of Section XI of the ASME Code.3.0NRC STAFF EVALUATION OF RR NO. ISI-35 3.1Information provided by Licensee The following information was provided by the licensee in the attachment to its applicationdated October 25, 2006, on RR ISI-35.
| |
|
| |
|
| ASME Code ComponentsThe component involved in the relief requests is the residual heat removal (RHR) Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W.ASME Code RequirementsThe applicable ASME Code requirements are the following:*ASME Code, Section XI, IWC-2500-1, Category C-A, Item C1.10 requiresvolumetric examination of essentially 100 percent of the weld length.*ASME Code Case N-460, Alternative Examination Coverage for Class 1 andClass 2 Welds, as an alternative approved for use by the NRC in Regulatory Guide(RG) 1.147, Revision 14, "Inservice Inspection Code Case Acceptability, ASME Section XII, Division 1," states that a reduction in examination coverage due to partgeometry or interference for any ASME Code Class 1 or 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained).Licensee's Basis for Relief Request In the attachment to its application for RR ISI-35, the licensee stated the following:The stainless steel flange configuration caused the examination to be single-sided. Theexamination was further obstructed by flange bolting. An additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination were performed to address the flange side of the weld. Conservatively, however, no credit was taken for the flange side of the weld because single-sided examinations of austenitic welds have not been adequately demonstrated in accordance with the 1The licensee's examination report for weld 2-EEJ01A-SEAM-1-W is not included in this safety evaluationand can be found in the licensee's letter dated October 26, 2006.requirements of ASME [Code] Section XI Appendix VIII. A copy of the examinationreport for the weld is attached.
| | ==1.0 INTRODUCTION== |
| 1There are currently no qualified single-side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications.Plant modifications or replacement with components designed to allow for completecoverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to Callaway Plant.Licensee's Proposed Alternative Examination (As Stated)In an attachment to its application for RR ISI-35, the licensee stated the following:The best available techniques, similar to those qualified through the industry'sPerformance Demonstration Initiative [PDI] for Supplement 2 with a demonstrated best effort for single-side examination, are used from the accessible side of the weld.3.2NRC Staff's Evaluation The ASME Code, Section XI, requires a volumetric examination of essentially 100 percentof the weld length for the RHR Heat Exchanger A bonnet flange-to-channel weld No. 2-EEJ01A-SEAM-1-W. The volumetric examination by ultrasonic methodology of this weld was conducted to the extent practical by the licensee using personnel, equipment, and procedures qualified in accordance with ASME Code, Section XI, Appendix VIII. The licenseefound that during the ultrasonic examination of the subject weld essentially 100-percent coverage of the required examination weld length could not be obtained. The ASME Code examination was limited due to the stainless steel flange configuration andflange bolting. As a result, the licensee was only able to perform the examination from the vessel side of the weld. The licensee also performed an additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination to address theflange side of the weld. The licensee did not take credit for the flange examinations because the single-sided examinations of austenitic welds have not been adequately demonstrated and there are not examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds at this time in accordance with the requirements of the ASME Code, Section XI, Appendix VIII. Therefore, the NRC staff determined that in order forthe licensee to obtain essentially 100-percent coverage of the required examination weld length, the RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W would have to be redesigned to allow greater access for scanning and would cause a burden on the
| |
|
| |
|
| licensee. The licensee obtained a composite coverage of 55 percent from the vessel side ofweld No. 2-EEJ01A-SEAM-1-W. Therefore, the NRC staff has determined that the examinations performed would have detected significant patterns of degradation, if any had occurred. The NRC staff has also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provide reasonable assurance of structural integrity of the weld.3.3Conclusion Based on the above evaluation, the NRC staff has reviewed the licensee's application forRR ISI-35 and concludes that the ASME Code examination coverage requirements are impractical for RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W for Callaway. Furthermore, based on the coverages obtained, if significant service-induced degradation were occurring, the NRC staff also concludes that there is reasonable assurance that evidence of it would have been detected by the examinations that were performed and that the volumetric examinations performed and VT-2 visual examinations during plant walkdowns provide reasonable assurance of structural integrity of weld 2-EEJ01A-SEAM-1-W.
| | By application dated October 25, 2006 (Agencywide Documents Access and Management System Accession No. ML063050203), Union Electric Company (the licensee) requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs) ISI-34, ISI-35, ISI-36, ISI-37, ISI-38, ISI-39, ISI-40, and ISI-41 were submitted in the letter. This safety evaluation addresses RR ISI-35. |
| | 2.0 REGULATORY REQUIREMENTS ISI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code and applicable addenda as required by paragraph 50.55a(g) of Title 10 of the Code of Federal Regulation (10 CFR). Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section XI, "Rules for Inservice Inspection 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 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) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. However, if a licensee determines that conformance with these requirements is impractical, it may request relief from these specific requirements. Pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant such relief and may impose alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the |
|
| |
|
| ==4.0CONCLUSION== | | public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. |
| Therefore, based on the above evaluation for RR No. ISI-35, relief is granted by theCommission, pursuant to 10 CFR 50.55a(g)(6)(i), on the basis that the ASME Code-required examination is impractical, for the second 10-year ISI interval for Callaway and that the proposed inspection provides reasonable assurance of structural integrity. The NRC staff has also determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR No. ISI-35 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 ASME Code, Section XI, requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: Tom McLellan Date: January 18, 2007}} | | The licensee stated that the ASME Code of record for the Callaway Plant second 10-year interval inservice inspection program is the 1989 Edition with no Addenda of Section XI of the ASME Code. |
| | 3.0 NRC STAFF EVALUATION OF RR NO. ISI-35 3.1 Information provided by Licensee The following information was provided by the licensee in the attachment to its application dated October 25, 2006, on RR ISI-35. |
| | ASME Code Components The component involved in the relief requests is the residual heat removal (RHR) Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W. |
| | ASME Code Requirements The applicable ASME Code requirements are the following: |
| | * ASME Code, Section XI, IWC-2500-1, Category C-A, Item C1.10 requires volumetric examination of essentially 100 percent of the weld length. |
| | * ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, as an alternative approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 14, Inservice Inspection Code Case Acceptability, ASME Section XII, Division 1, states that a reduction in examination coverage due to part geometry or interference for any ASME Code Class 1 or 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained). |
| | Licensees Basis for Relief Request In the attachment to its application for RR ISI-35, the licensee stated the following: |
| | The stainless steel flange configuration caused the examination to be single-sided. The examination was further obstructed by flange bolting. An additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination were performed to address the flange side of the weld. Conservatively, however, no credit was taken for the flange side of the weld because single-sided examinations of austenitic welds have not been adequately demonstrated in accordance with the |
| | |
| | requirements of ASME [Code] Section XI Appendix VIII. A copy of the examination report for the weld is attached.1 There are currently no qualified single-side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. |
| | Plant modifications or replacement with components designed to allow for complete coverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to Callaway Plant. |
| | Licensees Proposed Alternative Examination (As Stated) |
| | In an attachment to its application for RR ISI-35, the licensee stated the following: |
| | The best available techniques, similar to those qualified through the industry's Performance Demonstration Initiative [PDI] for Supplement 2 with a demonstrated best effort for single-side examination, are used from the accessible side of the weld. |
| | 3.2 NRC Staffs Evaluation The ASME Code, Section XI, requires a volumetric examination of essentially 100 percent of the weld length for the RHR Heat Exchanger A bonnet flange-to-channel weld No. 2-EEJ01A-SEAM-1-W. The volumetric examination by ultrasonic methodology of this weld was conducted to the extent practical by the licensee using personnel, equipment, and procedures qualified in accordance with ASME Code, Section XI, Appendix VIII. The licensee found that during the ultrasonic examination of the subject weld essentially 100-percent coverage of the required examination weld length could not be obtained. |
| | The ASME Code examination was limited due to the stainless steel flange configuration and flange bolting. As a result, the licensee was only able to perform the examination from the vessel side of the weld. The licensee also performed an additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination to address the flange side of the weld. The licensee did not take credit for the flange examinations because the single-sided examinations of austenitic welds have not been adequately demonstrated and there are not examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds at this time in accordance with the requirements of the ASME Code, Section XI, Appendix VIII. Therefore, the NRC staff determined that in order for the licensee to obtain essentially 100-percent coverage of the required examination weld length, the RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W would have to be redesigned to allow greater access for scanning and would cause a burden on the licensee. |
| | 1 The licensees examination report for weld 2-EEJ01A-SEAM-1-W is not included in this safety evaluation and can be found in the licensees letter dated October 26, 2006. |
| | |
| | The licensee obtained a composite coverage of 55 percent from the vessel side of weld No. 2-EEJ01A-SEAM-1-W. Therefore, the NRC staff has determined that the examinations performed would have detected significant patterns of degradation, if any had occurred. The NRC staff has also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provide reasonable assurance of structural integrity of the weld. |
| | 3.3 Conclusion Based on the above evaluation, the NRC staff has reviewed the licensee's application for RR ISI-35 and concludes that the ASME Code examination coverage requirements are impractical for RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W for Callaway. Furthermore, based on the coverages obtained, if significant service-induced degradation were occurring, the NRC staff also concludes that there is reasonable assurance that evidence of it would have been detected by the examinations that were performed and that the volumetric examinations performed and VT-2 visual examinations during plant walkdowns provide reasonable assurance of structural integrity of weld 2-EEJ01A-SEAM-1-W. |
| | |
| | ==4.0 CONCLUSION== |
| | |
| | Therefore, based on the above evaluation for RR No. ISI-35, relief is granted by the Commission, pursuant to 10 CFR 50.55a(g)(6)(i), on the basis that the ASME Code-required examination is impractical, for the second 10-year ISI interval for Callaway and that the proposed inspection provides reasonable assurance of structural integrity. The NRC staff has also determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR No. ISI-35 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 ASME Code, Section XI, requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: Tom McLellan Date: January 18, 2007}} |
Letter Sequence Other |
|---|
|
|
MONTHYEARML0630502032006-10-25025 October 2006
Callaway, Requests for Relief from ASME Section Xi Code Inservice Examination Requirements
Project stage: Request
ML0635203182007-01-18018 January 2007
Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval
Project stage: Other
2006-10-25
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML24225A1012024-08-13013 August 2024
Authorization and Safety Evaluation for Alternative Request C3R-01
ML24052A3662024-02-26026 February 2024
Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections
ML20225A2922020-08-12012 August 2020
Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI
ML19079A1482019-04-0101 April 2019
Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051
ML18313A0692018-11-26026 November 2018
Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping
ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds2018-04-0909 April 2018
Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds
ML17262A7002017-10-0303 October 2017
Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval
ML17254A1202017-09-25025 September 2017
Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval
ML17058A4432017-03-0606 March 2017
Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval
ML16223A7122016-08-30030 August 2016
Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval
ML16055A4642016-03-17017 March 2016
Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737)
ML16027A1582016-01-29029 January 2016
Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval
ML15064A1252015-05-12012 May 2015
Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval
ML15035A1482015-02-10010 February 2015
Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval
ML14239A0972014-09-0404 September 2014
Request for Relief I3R-15, ASME Code Class 1 Pressure-Retaining Piping/Components Leakage Testing at Full Pressure, Third 10-Year Inservice Inspection Interval
ML14234A4512014-09-0404 September 2014
Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval
ML14178A7692014-07-15015 July 2014
Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval
ML14027A0572014-01-29029 January 2014
Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
ML13246A3042013-08-30030 August 2013
Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
ML13126A3202013-05-0707 May 2013
Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval.
ML12258A0452012-09-18018 September 2012
Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks
ML1211502472012-05-0303 May 2012
Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks
ML1201907482012-02-16016 February 2012
Relief Request 13R-13, Alternative to ASME Code Section XI Requirements for Performance of Second Successive Exam of C Cold Leg Safe-End to Elbow Weld, Third 10-Year Inservice Inspection
ML0831002882008-11-0707 November 2008
Relief Request 13R-10 Approved on October 31, 2008, for Third 10-Year Inservice Inspection Interval for Use of Polyethylene Pipe in Lieu of Carbon Steel Pipe in Buried Essential Service Water Piping System
ML0818406062008-07-0303 July 2008
Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
ML0731114422007-12-10010 December 2007
Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval
ML0729803972007-10-30030 October 2007
Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval
ML0724000922007-09-17017 September 2007
Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval
ML0725504882007-08-30030 August 2007
10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Replacement of Class 3 Buried Piping
ML0715203292007-07-10010 July 2007
Request for Alternatives for Application of Structural Weld Overlays to Pressurizer Dissimilar Metal Nozzle Welds for Third 10-Year Inservice Inspection Program Interval
ML0705803332007-03-15015 March 2007
Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval
ML0635203182007-01-18018 January 2007
Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval
ML0700303362007-01-18018 January 2007
Relief Request ISI-41 for the Second 10-year Inservice Inspection Interval
ML0630604782006-12-0707 December 2006
Relief Request 13R-04 for the Third 10-Year Interval Inservice Inspection
ML0629302822006-11-17017 November 2006
Relief Requests I3R-05 and I3R-06 for the Third Inservice Inspection Interval
ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements2006-10-25025 October 2006
Requests for Relief from ASME Section XI Code Inservice Examination Requirements
ML0614301312006-06-15015 June 2006
Relief, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02
ML0520802152005-08-18018 August 2005
Relief, Use a Subsequent Edition of ASME Code Examinations for the Third Inservice Inspection Interval
ML0515302072005-06-22022 June 2005
6/22/05 Callaway, Unit 1 - Relief Requests ISI-24,ISI-25 and ISI-26 of the Second 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4435 and MC4436)
ML0507601292005-05-19019 May 2005
Relief, Request for Relief from Certain ASME Code Examinations for the Second Inservice Inspection Interval
ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program2004-11-18018 November 2004
Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program
ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements2004-09-0303 September 2004
Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements
ML0414100712004-05-19019 May 2004
Relief, ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping.
ML0414100352004-05-19019 May 2004
Relief, Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method
ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement2004-05-0707 May 2004
Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement
ML0409806642004-04-0707 April 2004
4/7/04 Callaway Plant - Request for Relief from ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping
ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements2003-08-14014 August 2003
Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements
ML0318305352003-07-0101 July 2003
Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method (Tac. MB6534)
ML0134602652002-01-30030 January 2002
Relief, Application of Risk-Informed Inservice Inspection Program for the American Society of Mechanical Engineers Boilers and Pressure Vessel Code Class 1 and 2 TAC No MB1205)
2024-08-13
[Table view]
Category:Letter
MONTHYEARIR 05000483/20240032024-10-23023 October 2024
Integrated Inspection Report 05000483/2024003
IR 05000483/20240132024-10-21021 October 2024
Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2024013
IR 05000483/20244012024-10-0909 October 2024
Material Control and Accounting Program Inspection Report 05000483/2024401 Public
ULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024
Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)
ML24247A3042024-09-11011 September 2024
Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary
IR 05000483/20244032024-08-28028 August 2024
Security Baseline Inspection 05000483-2024-403
IR 05000483/20240052024-08-14014 August 2024
Updated Inspection Plan for Callaway Plant (Report 05000483/2024005)
IR 05000483/20253012024-08-0505 August 2024
Notification of NRC Initial Operator Licensing Examination 05000483/2025301
ML24212A2822024-08-0202 August 2024
Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections
IR 05000483/20240022024-07-18018 July 2024
And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001
ML24185A1032024-07-16016 July 2024
2024 Biennial Problem Identification and Resolution Inspection Report
ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005
ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024
Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006
ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002
ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003
ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004
ML24144A0492024-06-11011 June 2024
Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval
ML24158A5222024-06-0606 June 2024
Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008)
ML24178A1132024-06-0606 June 2024
Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site
ML24143A1632024-05-23023 May 2024
Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001
ML24137A2342024-05-16016 May 2024
Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011
ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024
Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012
ML24122A1502024-05-0707 May 2024
Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35
IR 05000483/20244022024-05-0606 May 2024
Security Baseline Inspection Report 05000483/2024402 (Full Report)
ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024
Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25
ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024
CFR 50.59 and 10 CFR 72.48 Summary Report
IR 05000483/20240112024-05-0101 May 2024
NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011
ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024
Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report
ML24122A1132024-04-30030 April 2024
Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report
ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024
Registration of Dry Spent Fuel Storage Canister HGMPC0010
ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024
Submittal of Cycle 26 Commitment Change Summary Report
ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007
ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024
Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008
ML24108A1082024-04-17017 April 2024
Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009
IR 05000483/20240012024-04-16016 April 2024
Integrated Inspection Report 05000483/2024001
IR 05000483/20244042024-04-0909 April 2024
Cyber Security Inspection Report 05000483/2024404
ML24088A3212024-04-0101 April 2024
Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information
ML24086A5132024-03-26026 March 2024
CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions
ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024
Submittal of Annual Exposure Report for 2023
ML24079A1622024-03-19019 March 2024
Re Nuclear Property Insurance Reporting
ML24066A1932024-03-0707 March 2024
2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information
ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024
Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26
IR 05000483/20230062024-02-28028 February 2024
Annual Assessment Letter for Callaway Plant Report 05000483/2023006
ML24052A3662024-02-26026 February 2024
Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections
IR 05000483/20230022024-02-21021 February 2024
Amended Integrated Inspection Report 05000483/2023002
ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024
Completion of License Renewal Activities Prior to Entering the Period of Extended Operation
ML24036A1712024-02-20020 February 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024
Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717
ML24008A0552024-01-19019 January 2024
Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061)
IR 05000483/20230042024-01-19019 January 2024
– Integrated Inspection Report 05000483/2023004
2024-09-11
[Table view]
Category:Safety Evaluation
MONTHYEARML23353A1712024-01-18018 January 2024
Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6
ML23347A1212024-01-11011 January 2024
Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046)
ML23234A1522023-10-0505 October 2023
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter)
ML23240A3692023-10-0505 October 2023
Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary)
ML23228A0252023-09-25025 September 2023
Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
ML23261C3852023-09-25025 September 2023
Safety Evaluation for Operating Quality Assurance Manual Revision 36A
ML23166B0882023-09-20020 September 2023
Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications
ML22361A0702023-02-24024 February 2023
Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals
ML23019A1752023-01-30030 January 2023
Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML22301A0072022-12-0202 December 2022
Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2
ML22220A1302022-10-21021 October 2022
Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter)
ML22220A1322022-10-21021 October 2022
Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach
ML22053A2832022-04-0707 April 2022
Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules
ML21344A0052021-12-29029 December 2021
Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants
ML21053A1262021-03-24024 March 2021
Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff
ML20218A4102020-11-0303 November 2020
Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material
ML20246G5702020-10-16016 October 2020
Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections
ML20230A3872020-08-31031 August 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20216A6812020-08-0606 August 2020
Operating Quality Assurance Manual Change Revision 34B (EPID L-2020-LLQ-0004 (COVID-19))
ML20141L7452020-06-0808 June 2020
Operating Quality Assurance Manual Change Revision 34A
ML20107H9782020-04-20020 April 2020
COVID-19 Relief Request CC-01 Containment Tendon Inspection
ML19283C4812019-12-0606 December 2019
Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing
ML19158A2902019-07-30030 July 2019
Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes
ML19073A0012019-04-18018 April 2019
Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System
ML19079A1482019-04-0101 April 2019
Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051
ML18313A0692018-11-26026 November 2018
Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping
ML18124A0262018-05-30030 May 2018
Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection
ML17262A7002017-10-0303 October 2017
Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval
ML17254A1202017-09-25025 September 2017
Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval
ML17236A0822017-09-15015 September 2017
Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr),
ML17170A3202017-06-20020 June 2017
Safety Evaluation Input - for Ameren Missouri Request to Amend Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report -
ML17058A4432017-03-0606 March 2017
Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval
ML17010A3322017-02-0202 February 2017
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16223A7122016-08-30030 August 2016
Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval
ML16089A1672016-04-0101 April 2016
Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1
ML16055A4642016-03-17017 March 2016
Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737)
ML16020A5162016-02-29029 February 2016
Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology
ML15324A1142016-02-0202 February 2016
Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
ML16027A1582016-01-29029 January 2016
Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval
ML15328A0592016-01-28028 January 2016
Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date
ML15258A5102015-10-28028 October 2015
Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation
ML15251A4932015-10-0707 October 2015
Issuance of Amendment No. 212, Request to Upgrade the Emergency Action Level Scheme by Adopting Nuclear Energy Institute NEI 99-01, Revision 6
ML15064A1252015-05-12012 May 2015
Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval
ML15064A0282015-03-31031 March 2015
Issuance of Amendment No. 211, Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion
ML15035A1482015-02-10010 February 2015
Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval
ML14350B2392015-01-20020 January 2015
Issuance of Amendment No. 210, Revise Technical Specification LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4-6
ML14234A4512014-09-0404 September 2014
Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval
ML14178A7692014-07-15015 July 2014
Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval
ML14175A3902014-07-0101 July 2014
Issuance of Amendment No. 209, Adoption of Technical Specification Task Force Change Traveler TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using CLIIP
ML14027A0572014-01-29029 January 2014
Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
2024-01-18
[Table view] |
Text
January 18, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - REQUEST FOR RELIEF NO. ISI-35 FOR SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3434)
Dear Mr. Naslund:
By letter dated October 25, 2006 (ULNRC-05183), the Union Electric Company (the licensee) requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs)
ISI-34, ISI-35, ISI-36, ISI-37, SI-38, ISI-39, ISI-40, and ISI-41 were submitted in that letter. This letter addresses RR ISI-35.
Based on the attached safety evaluation, the Nuclear Regulatory Commission (NRC) staff has determined that the ASME Code examination coverage requirements are impractical for the subject weld listed in RR ISI-35, and that the proposed inspection provides reasonable assurance of structural integrity. Therefore, granting relief, pursuant to paragraph 50.55a(g)(6)(i) of Title 10 of the Code of Federal Regulations, 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, the NRC staff grants the relief in RR ISI-35 for the second 10-year ISI interval at Callaway. 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.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Safety Evaluation cc w/encl: See next page
ML063520318 OFFICE NRR/LPL4/PM NRR/LPL4/LA CVIB/BC OGC-NLO w/comments NRR/LPL4/BC NAME JDonohew LFeizollahi MMitchell JRund DTerao DATE 12/21/07 12/19/07 12/12/06 1/2/07 1/18/07
Callaway Plant, Unit 1 cc:
Professional Nuclear Consulting, Inc. Mr. Dan I. Bolef, President 19041 Raines Drive Kay Drey, Representative Derwood, MD 20855 Board of Directors Coalition for the Environment John ONeill, Esq. 6267 Delmar Boulevard Pillsbury Winthrop Shaw Pittman LLP University City, MO 63130 2300 N. Street, N.W.
Washington, D.C. 20037 Mr. Lee Fritz, Presiding Commissioner Callaway County Court House Mr. Keith A. Mills, Supervising Engineer 10 East Fifth Street Regional Regulatory Affairs/Safety Analysis Fulton, MO 65151 AmerenUE P.O. Box 620 Mr. David E. Shafer Fulton, MO 65251 Superintendent, Licensing Regulatory Affairs U.S. Nuclear Regulatory Commission AmerenUE Resident Inspector Office P.O. Box 66149, MC 470 8201 NRC Road St. Louis, MO 63166-6149 Steedman, MO 65077-1302 Manager, Regulatory Affairs Mr. Les H. Kanuckel AmerenUE Manager, Quality Assurance P.O. Box 620 AmerenUE Fulton, MO 65251 P.O. Box 620 Fulton, MO 65251 Mr. Keith G. Henke, Planner Division of Community and Public Health Missouri Public Service Commission Office of Emergency Coordination Governor Office Building 930 Wildwood P.O. Box 570 200 Madison Street Jefferson City, MO 65102 Jefferson City, MO 65102-0360 Certrec Corporation Regional Administrator, Region IV 4200 South Hulen, Suite 630 U.S. Nuclear Regulatory Commission Fort Worth, TX 76109 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Director, Missouri State Emergency Management Agency Mr. H. Floyd Gilzow P.O. Box 116 Deputy Director for Policy Jefferson City, MO 65102-0116 Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839 June 2006
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SECOND 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. ISI-35 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By application dated October 25, 2006 (Agencywide Documents Access and Management System Accession No. ML063050203), Union Electric Company (the licensee) requested relief from certain examination requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (i.e., the ASME Code) for the second 10-year inservice inspection (ISI) interval at the Callaway Plant (Callaway). Relief Requests (RRs) ISI-34, ISI-35, ISI-36, ISI-37, ISI-38, ISI-39, ISI-40, and ISI-41 were submitted in the letter. This safety evaluation addresses RR ISI-35.
2.0 REGULATORY REQUIREMENTS ISI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code and applicable addenda as required by paragraph 50.55a(g) of Title 10 of the Code of Federal Regulation (10 CFR). Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection 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 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) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. However, if a licensee determines that conformance with these requirements is impractical, it may request relief from these specific requirements. Pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant such relief and may impose alternative requirements as it determines 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.
The licensee stated that the ASME Code of record for the Callaway Plant second 10-year interval inservice inspection program is the 1989 Edition with no Addenda of Section XI of the ASME Code.
3.0 NRC STAFF EVALUATION OF RR NO. ISI-35 3.1 Information provided by Licensee The following information was provided by the licensee in the attachment to its application dated October 25, 2006, on RR ISI-35.
ASME Code Components The component involved in the relief requests is the residual heat removal (RHR) Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W.
ASME Code Requirements The applicable ASME Code requirements are the following:
- ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, as an alternative approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 14, Inservice Inspection Code Case Acceptability, ASME Section XII, Division 1, states that a reduction in examination coverage due to part geometry or interference for any ASME Code Class 1 or 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90-percent examination coverage is obtained).
Licensees Basis for Relief Request In the attachment to its application for RR ISI-35, the licensee stated the following:
The stainless steel flange configuration caused the examination to be single-sided. The examination was further obstructed by flange bolting. An additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination were performed to address the flange side of the weld. Conservatively, however, no credit was taken for the flange side of the weld because single-sided examinations of austenitic welds have not been adequately demonstrated in accordance with the
requirements of ASME [Code] Section XI Appendix VIII. A copy of the examination report for the weld is attached.1 There are currently no qualified single-side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications.
Plant modifications or replacement with components designed to allow for complete coverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to Callaway Plant.
Licensees Proposed Alternative Examination (As Stated)
In an attachment to its application for RR ISI-35, the licensee stated the following:
The best available techniques, similar to those qualified through the industry's Performance Demonstration Initiative [PDI] for Supplement 2 with a demonstrated best effort for single-side examination, are used from the accessible side of the weld.
3.2 NRC Staffs Evaluation The ASME Code,Section XI, requires a volumetric examination of essentially 100 percent of the weld length for the RHR Heat Exchanger A bonnet flange-to-channel weld No. 2-EEJ01A-SEAM-1-W. The volumetric examination by ultrasonic methodology of this weld was conducted to the extent practical by the licensee using personnel, equipment, and procedures qualified in accordance with ASME Code,Section XI, Appendix VIII. The licensee found that during the ultrasonic examination of the subject weld essentially 100-percent coverage of the required examination weld length could not be obtained.
The ASME Code examination was limited due to the stainless steel flange configuration and flange bolting. As a result, the licensee was only able to perform the examination from the vessel side of the weld. The licensee also performed an additional 45-degree full-vee shear wave examination and a 45-degree half-vee longitudinal wave examination to address the flange side of the weld. The licensee did not take credit for the flange examinations because the single-sided examinations of austenitic welds have not been adequately demonstrated and there are not examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic welds at this time in accordance with the requirements of the ASME Code,Section XI, Appendix VIII. Therefore, the NRC staff determined that in order for the licensee to obtain essentially 100-percent coverage of the required examination weld length, the RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W would have to be redesigned to allow greater access for scanning and would cause a burden on the licensee.
1 The licensees examination report for weld 2-EEJ01A-SEAM-1-W is not included in this safety evaluation and can be found in the licensees letter dated October 26, 2006.
The licensee obtained a composite coverage of 55 percent from the vessel side of weld No. 2-EEJ01A-SEAM-1-W. Therefore, the NRC staff has determined that the examinations performed would have detected significant patterns of degradation, if any had occurred. The NRC staff has also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provide reasonable assurance of structural integrity of the weld.
3.3 Conclusion Based on the above evaluation, the NRC staff has reviewed the licensee's application for RR ISI-35 and concludes that the ASME Code examination coverage requirements are impractical for RHR Heat Exchanger A bonnet flange-to-channel weld 2-EEJ01A-SEAM-1-W for Callaway. Furthermore, based on the coverages obtained, if significant service-induced degradation were occurring, the NRC staff also concludes that there is reasonable assurance that evidence of it would have been detected by the examinations that were performed and that the volumetric examinations performed and VT-2 visual examinations during plant walkdowns provide reasonable assurance of structural integrity of weld 2-EEJ01A-SEAM-1-W.
4.0 CONCLUSION
Therefore, based on the above evaluation for RR No. ISI-35, relief is granted by the Commission, pursuant to 10 CFR 50.55a(g)(6)(i), on the basis that the ASME Code-required examination is impractical, for the second 10-year ISI interval for Callaway and that the proposed inspection provides reasonable assurance of structural integrity. The NRC staff has also determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR No. ISI-35 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 ASME Code,Section XI, requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Tom McLellan Date: January 18, 2007
