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| {{#Wiki_filter:January 3, 2006Mr. H. L. Sumner, Jr. | | {{#Wiki_filter:January 3, 2006 Mr. H. L. Sumner, Jr. |
| Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc. | | Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc. |
| P.O. Box 1295 Birmingham, AL 35201-1295 | | P.O. Box 1295 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUESTFOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSELCODE (CODE) (TAC NOS. MC6528 AND MC6529). | | EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE (CODE) (TAC NOS. MC6528 AND MC6529). |
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| ==Dear Mr. Sumner:== | | ==Dear Mr. Sumner:== |
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| By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, andOctober 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted aproposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria fromTitle 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to theexamination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief requestISI-ALT-1. The request is for the fourth 10-year inservice inspection interval. The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1,Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensee's proposed alternative provides an acceptable level of quality and safety. The NRC staffauthorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch.The NRC staff's safety evaluation is enclosed.Sincerely,/RA/Evangelos C. Marinos, ChiefPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-321 and 50-366 | | By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted a proposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria from Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection interval. |
| | The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1, Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensees proposed alternative provides an acceptable level of quality and safety. The NRC staff authorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch. |
| | The NRC staff's safety evaluation is enclosed. |
| | Sincerely, |
| | /RA/ |
| | Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next page January 3, 2006Mr. H. L. Sumner, Jr. | | Safety Evaluation cc w/encl: See next page |
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| | January 3, 2006 Mr. H. L. Sumner, Jr. |
| Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc. | | Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc. |
| P.O. Box 1295 Birmingham, AL 35201-1295 | | P.O. Box 1295 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUESTFOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSELCODE (CODE) (TAC NOS. MC6528 AND MC6529). | | EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE (CODE) (TAC NOS. MC6528 AND MC6529). |
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| ==Dear Mr. Sumner:== | | ==Dear Mr. Sumner:== |
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| By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, andOctober 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted aproposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria fromTitle 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to theexamination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief requestISI-ALT-1. The request is for the fourth 10-year inservice inspection interval. The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1,Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensee's proposed alternative provides an acceptable level of quality and safety. The NRC staffauthorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch.The NRC staff's safety evaluation is enclosed.Sincerely,/RA/ | | By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted a proposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria from Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection interval. |
| Evangelos C. Marinos, ChiefPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-321 and 50-366 | | The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1, Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensees proposed alternative provides an acceptable level of quality and safety. The NRC staff authorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch. |
| | The NRC staff's safety evaluation is enclosed. |
| | Sincerely, |
| | /RA/ |
| | Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next pageDISTRIBUTION: | | Safety Evaluation cc w/encl: See next page DISTRIBUTION: |
| PublicRidsOgcRpLPL2-1ReadingDNaujock RidsAcrsAcnwMailCenterRidsNrrLAMO'BrienBWetzel, EDO RIIRidsNrrPMGrattonRidsAcrsRgn2MailCenter(MWidmann)RidsNrrDorlLplc(EMarinos)RidsNrrDciCpnb(TChan)RidsNrrDprAccession No. ML053470091NRR_028OFFICENRR/LPL2-1/PMNRR/LPL2-1/LANRR/CPNB/BCOGC NRR/LPL2-1/BCNAMECGratton:kgMO'BrienTChanS. HamrickEMarinosDATE12/22/0501/03/06SE dated 12/12/0512/16/0501/03/06OFFICIAL RECORD COPY SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST ISI-ALT-1, VERSION 4.0SOUTHERN NUCLEAR OPERATING COMPANY, INC.EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 (HATCH)DOCKET NOS. 50-321 AND 50-36
| | Public RidsOgcRp LPL2-1Reading DNaujock RidsAcrsAcnwMailCenter RidsNrrLAMOBrien BWetzel, EDO RII RidsNrrPMGratton RidsAcrsRgn2MailCenter(MWidmann) RidsNrrDorlLplc(EMarinos) RidsNrrDciCpnb(TChan) RidsNrrDpr Accession No. ML053470091 NRR_028 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CPNB/BC OGC NRR/LPL2-1/BC NAME CGratton:kg MOBrien TChan S. Hamrick EMarinos DATE 12/22/05 01/03/06 SE dated 12/16/05 01/03/06 12/12/05 OFFICIAL RECORD COPY |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST ISI-ALT-1, VERSION 4.0 SOUTHERN NUCLEAR OPERATING COMPANY, INC. |
| | EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 (HATCH) |
| | DOCKET NOS. 50-321 AND 50-366 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee) submitted a request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code). Specifically, the licensee proposed using ASME Code, Section XI, Appendix VIII, Supplements 4 and 6 qualified procedures and personnel, and the criteria from the Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a that are applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection (ISI) interval which begins January 1, 2006, and ends December 31, 2015. |
| | 2.0 REGULATORY REQUIREMENTS The ISI of ASME Code Class 1, Class 2, and Class 3 components will be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Section 50.55a(a)(3) states in part that alternatives to the requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, Class 2, and Class 3 components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code, Section XI, Rules for Inservice Inspection 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 ISI 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, |
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| | subject to the limitations and modifications listed therein. The ASME Code of record for Hatch for the fourth 10-year ISI interval is the 2001 edition through the 2003 addenda of the ASME Code. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | 3.1 Component for Which Relief is Requested The applicable vessel welds are ASME Code Class 1, Category B-A pressure retaining welds in the RPV, Item No. B1.30, shell-to-flange weld, and Item No. B1.40, head-to-flange weld. |
| | 3.2 Applicable ASME Code Requirements The applicable requirement is the 2001 edition through the 2003 addenda of Section XI of the ASME Code, Appendix I, I-2120, which states that vessels greater than 2 inches in thickness shall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1. |
| | 3.3 Licensees Proposed Alternative The licensee proposed performing ultrasonic test (UT) examinations of the subject welds in accordance with the 2001 edition with the 2003 addenda of ASME Code, Section XI, with the modifications and limitations listed in the 10 CFR 50.55a. The licensee will use personnel and procedures qualified to the 2001 edition with no addenda, Section XI, Appendix VIII, Supplement 4, Qualification Requirements for the Clad/Base Metal Interface of Reactor Vessel, and Supplement 6, Qualification Requirements for Reactor Vessel Welds other than Clad/Base Metal Interface, as administered by the Energy Power Research Institute - |
| | Performance Demonstration Initiative (PDI) Program. |
| | 3.4 Licensees Basis for Relief Appendix VIII requirements were developed with a rigorous, item-specific performance demonstration to ensure the effectiveness of UT examinations. The performance demonstration administered by PDI was conducted on RPV mockups containing flaws of various size and allocations. The demonstration established the capability of equipment, procedures, and personnel to find flaws that could be detrimental to the integrity of the RPV. |
| | The performance demonstration showed that for the detection of flaws in RPV welds, the UT techniques were equal to or surpassed the requirements of the Section V, Article 4 of the ASME Code. Additionally, the PDI qualified sizing techniques are considered to be more accurate than the techniques used in Section V, Article 4. |
| | Although Appendix VIII is not required for the RPV shell-to-flange and RPV head-to-flange welds, the use of Appendix VIII, Supplements 4 and 6 criteria for detection of flaws in these welds will be equal to or will exceed the requirements established by Section V, Article 4. |
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| ==61.0 INTRODUCTION==
| | 3.5 NRC Staff Evaluation The 2001 edition, 2003 addenda of ASME Code, Section XI, IWA-2232 states, Ultrasonic examination shall be conducted in accordance with Appendix I. Subarticle I-2120 states that vessels greater than 2 inches in thickness shall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1. Section V, Article 4 provides a prescriptive-based process for qualifying UT of procedures and the scanning requirements for examinations. The prescriptive-based UT uses detailed criteria for setting up and calibrating equipment, calculating coverage, and detecting indications. The capability of a prescriptive-based UT examination is demonstrated with calibration blocks made from representative material containing holes and notches. Performance-based UT requires that detailed criteria be used for performance demonstration tests. The results for the tests are compared against statistically developed screening criteria. The tests are performed on representative mockups containing flaws similar to those found in operating plants. The performance-based tests demonstrate the effectiveness of UT personnel and procedures. |
| By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, andOctober 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee) submitted arequest for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME), Boiler and PressureVessel Code (Code). Specifically, the licensee proposed using ASME Code, Section XI,Appendix VIII, Supplements 4 and 6 qualified procedures and personnel, and the criteria fromthe Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a that areapplicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for reliefrequest ISI-ALT-1. The request is for the fourth 10-year inservice inspection (ISI) interval which begins January 1, 2006, and ends December 31, 2015. 2.0 REGULATORY REQUIREMENTSThe ISI of ASME Code Class 1, Class 2, and Class 3 components will be performed inaccordance with Section XI of the ASME Code and applicable edition and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Section 50.55a(a)(3) states in part that alternatives to therequirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if the licensee demonstrates that: (i) the proposed alternatives wouldprovide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, Class 2, and Class 3 components(including supports) will meet the requirements, except the design and access provisions andthe preservice 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 com ponents and system pressure testsconducted during the first 10-year ISI 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. The ASME Code of record for Hatchfor the fourth 10-year ISI interval is the 2001 edition through the 2003 addenda of the ASME Code. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
| | In lieu of Subarticle I-2120, the licensee proposed performing UT examinations of the subject welds in accordance with the 2001 edition, 2003 addenda of ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a. Section 50.55a limits the use of Appendix VIII to the 2001 edition with no addenda. Appendix VIII is a performance-based UT method. Examinations are performed with the scanning requirements for Supplements 4 and 6 that are provided in 10 CFR 50.55a(b)(2)(xv)(G), and the scanning volume identified in the ASME Code, Section XI, Figure IWB-2500-4 for the shell-to-flange weld and Figure IWB-2500-5 for the head-to-flange weld. The scanning requirements are: (1) for the examination of the inner 15 percent through-wall volume, scanning will be performed in four orthogonal directions to the maximum extent possible with procedures and personnel qualified to Appendix VIII, Supplement 4; (2) the remainder of the inner 15 percent through-wall volume is considered fully examined if coverage is obtained in at least one parallel and one perpendicular direction using personnel and procedures qualified for single side examination in accordance with Supplement 6; and (3) the remaining 85 percent through-wall volume is considered fully examined if coverage is obtained in one parallel and one perpendicular direction using procedures and personnel qualified for single side examination. Single side qualification criteria are provided in 10 CFR 50.55a(b)(2)(xv)(G)(2) and 10 CFR 50.55a(b)(2)(xvi). |
| | The licensee will follow 10 CFR 50.55a(b)(2)(xv)(G) for the vessel-to-flange and head-to-flange welds. Because the head-to-flange weld has no cladding, the licensee will use Code Case N-664, Performance Demonstration Requirements for Examination of Unclad Reactor Pressure Vessel Welds, Excluding Flange Welds, that permits using Appendix VIII, Supplement 4 in lieu of the requirements of Appendix VIII, Supplement 6 for the inner 10 percent performance demonstration. Code Case N-664 is endorsed in Regulatory Guide, 1.147, Revision 14, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1. There are no specific performance demonstration requirements from 10 percent through 15 percent through-wall thickness. The scanning of the uncladded head-to-flange weld would be applied according to the requirements of 10 CFR 50.55a(b)(2)(xv)(G). |
| | The procedures, equipment, and personnel qualified to Appendix VIII through the PDI program have shown a high probability of flaw detection, and have increased the reliability of |
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| ==3.0 TECHNICAL EVALUATION==
| | examinations of weld configurations within the scope of the PDI program. Therefore, the proposed alternative will provide an acceptable level of quality and safety. |
| 3.1Component for Which Relief is RequestedThe applicable vessel welds are ASME Code Class 1, Category B-A pressure retaining welds inthe RPV, Item No. B1.30, shell-to-flange weld, and Item No. B1.40, head-to-flange weld.3.2Applicable ASME Code RequirementsThe applicable requirement is the 2001 edition through the 2003 addenda of Section XI of theASME Code, Appendix I, I-2120, which states that vessels greater than 2 inches in thicknessshall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1.3.3Licensee's Proposed AlternativeThe licensee proposed performing ultrasonic test (UT) examinations of the subject welds inaccordance with the 2001 edition with the 2003 addenda of ASME Code, Section XI, with the modifications and limitations listed in the 10 CFR 50.55a. The licensee will use personnel andprocedures qualified to the 2001 edition with no addenda, Section XI, Appendix V III,Supplement 4, "Qualification Requirements for the Clad/Base Metal Interface of ReactorVessel," and Supplement 6, "Qualification Requirements for Reactor Vessel Welds other thanClad/Base Metal Interface," as administered by the Energy Power Research Institute -
| | 4.0 Conclusion Based on the above evaluation, the NRC staff concludes that the licensees proposed alternative, ISI-ALT-1, Version 4.0, to use the 2001 edition of the ASME Code, Section XI, Appendix VIII, Supplements 4 and 6 as modified by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xvi) for the RPV shell-to-flange and head-to-flange welds will provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for Hatch for the fourth 10-year inservice inspection interval. |
| Performance Demonstration Initiative (PDI) Program. 3.4Licensee's Basis for ReliefAppendix VIII requirements were developed with a rigorous, item-specific performancedemonstration to ensure the effectiveness of UT examinations. The performance demonstration administered by PDI was conducted on RPV mockups containing flaws of various size and allocations. The demonstration established the capability of equipment,procedures, and personnel to find flaws that could be detrimental to the integrity of the RPV. The performance demonstration showed that for the detection of flaws in RPV welds, the UT techniques were equal to or surpassed the requirements of the Section V, Article 4 of the ASME Code. Additionally, the PDI qualified sizing techniques are considered to be more accurate than the techniques used in Section V, Article 4.Although Appendix VIII is not required for the RPV shell-to-flange and RPV head-to-flangewelds, the use of Appendix VIII, Supplements 4 and 6 criteria for detection of flaws in thesewelds will be equal to or will exceed the requirements established by Section V, Article 4. 3.5NRC Staff EvaluationThe 2001 edition, 2003 addenda of ASME Code, Section XI, IWA-2232 states, "Ultrasonicexamination shall be conducted in accordance with Appendix I." Subarticle I-2120 states that vessels greater than 2 inches in thickness shall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1. Section V, Article 4 provides a prescriptive-based process for qualifying UT of procedures and the scanning requirements for examinations. The prescriptive-based UT uses detailed criteria for setting up and calibrating equipment, calculating coverage, and detecting indications. The capability of aprescriptive-based UT examination is demonstrated with calibration blocks made fromrepresentative material containing holes and notches. Performance-based UT requires that detailed criteria be used for performance demonstration tests. The results for the tests are compared against statistically developed screening criteria. The tests are performed on representative mockups containing flaws similar to those found in operating plants. Theperformance-based tests demonstrate the effectiveness of UT personnel and procedures.In lieu of Subarticle I-2120, the licensee proposed performing UT examinations of the subjectwelds in accordance with the 2001 edition, 2003 addenda of ASME Code, Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a. Section 50.55a limits the use ofAppendix VIII to the 2001 edition with no addenda. Appendix VIII is a performance-based UTmethod. Examinations are performed with the scanning requirements for Supplements 4 and 6that are provided in 10 CFR 50.55a(b)(2)(xv)(G), and the scanning volume identified in the ASME Code, Section XI, Figure IWB-2500-4 for the shell-to-flange weld and Figure IWB-2500-5 for the head-to-flange weld. The scanning requirements are: (1) for the examination of the inner 15 percent through-wall volume, scanning will be performed in fourorthogonal directions to the maximum extent possible with procedures and personnel qualified to Appendix VIII, Supplement 4; (2) the remainder of the inner 15 percent through-wall volumeis considered fully examined if coverage is obtained in at least one parallel and one perpendicular direction using personnel and procedures qualified for single side examination in accordance with Supplement 6; and (3) the remaining 85 percent through-wall volume is considered fully examined if coverage is obtained in one parallel and one perpendicular direction using procedures and personnel qualified for single side examination. Single side qualification criteria are provided in 10 CFR 50.55a(b)(2)(xv)(G)(2) and 10 CFR 50.55a(b)(2)(xvi).The licensee will follow 10 CFR 50.55a(b)(2)(xv)(G) for the vessel-to-flange and head-to-flangewelds. Because the head-to-flange weld has no cladding, the licensee will use Code Case N-664, "Performance Demonstration Requirements for Examination of Unclad Reactor Pressure Vessel Welds, Excluding Flange Welds," that permits using Appendix V III,Supplement 4 in lieu of the requirements of Appendix VIII, Supplement 6 for the inner10 percent performance demonstration. Code Case N-664 is endorsed in Regulatory Guide, 1.147, Revision 14, "Inservice Inspection Code Case Acceptability, ASME Section XI,Division 1." There are no specific performance demonstration requirements from 10 percent through 15 percent through-wall thickness. The scanning of the uncladded head-to-flange weld would be applied according to the requirements of 10 CFR 50.55a(b)(2)(xv)(G).The procedures, equipment, and personnel qualified to Appendix VIII through the PDI programhave shown a high probability of flaw detection, and have increased the reliability of examinations of weld configurations within the scope of the PDI program. Therefore, theproposed alternative will provide an acceptable level of quality and safety. 4.0 ConclusionBased on the above evaluation, the NRC staff concludes that the licensee's proposedalternative, ISI-ALT-1, Version 4.0, to use the 2001 edition of the ASME Code, Section XI,Appendix VIII, Supplements 4 and 6 as modified by 10 CFR 50.55a(b)(2)(xv) and 10 CFR50.55a(b)(2)(xvi) for the RPV shell-to-flange and head-to-flange welds will provide anacceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for Hatch for the fourth 10-year inservice inspection interval.All other requirements of the ASME Code for which relief has not been specifically requestedremain applicable, including third party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: Donald Naujock, NRR Date: January 3, 2006
| | All other requirements of the ASME Code for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: Donald Naujock, NRR Date: January 3, 2006 |
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| Edwin I. Hatch Nuclear Plant, Units 1 & 2 cc: | | Edwin I. Hatch Nuclear Plant, Units 1 & 2 cc: |
| Laurence BergenOglethorpe Power Corporation 2100 E. Exchange Place P.O. Box 1349 Tucker, GA 30085-1349Mr. R.D. BakerManager - Licensing Southern Nuclear Operating Company, Inc. | | Laurence Bergen Chairman Oglethorpe Power Corporation Appling County Commissioners 2100 E. Exchange Place County Courthouse P.O. Box 1349 Baxley, GA 31513 Tucker, GA 30085-1349 Mr. Jeffrey T. Gasser Mr. R.D. Baker Executive Vice President Manager - Licensing Southern Nuclear Operating Company, Inc. |
| P.O. Box 1295 Birmingham, AL 35201-1295Resident InspectorPlant Hatch 11030 Hatch Parkway N. | | Southern Nuclear Operating Company, Inc. P.O. Box 1295 P.O. Box 1295 Birmingham, AL 35201-1295 Birmingham, AL 35201-1295 Mr. G. R. Frederick, General Manager Resident Inspector Edwin I. Hatch Nuclear Plant Plant Hatch Southern Nuclear Operating Company, Inc. |
| Baxley, GA 31531Harold Reheis, DirectorDepartment of Natural Resources 205 Butler Street, SE., Suite 1252 Atlanta, GA 30334Steven M. JacksonSenior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684Mr. Reece McAlisterExecutive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334Arthur H. Domby, Esq.Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216ChairmanAppling County Commissioners County Courthouse Baxley, GA 31513Mr. Jeffrey T. GasserExecutive Vice President Southern Nuclear Operating Company, Inc. | | 11030 Hatch Parkway N. U.S. Highway 1 North Baxley, GA 31531 P.O. Box 2010 Baxley, GA 31515 Harold Reheis, Director Department of Natural Resources Mr. K. Rosanski 205 Butler Street, SE., Suite 1252 Resident Manager Atlanta, GA 30334 Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant Steven M. Jackson P.O. Box 2010 Senior Engineer - Power Supply Baxley, GA 31515 Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334 Arthur H. Domby, Esq. |
| P.O. Box 1295 Birmingham, AL 35201-1295Mr. G. R. Frederick, General ManagerEdwin I. Hatch Nuclear Plant Southern Nuclear Operating Company, Inc.
| | Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216}} |
| U.S. Highway 1 North P.O. Box 2010 Baxley, GA 31515Mr. K. RosanskiResident Manager Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant P.O. Box 2010 Baxley, GA 31515}}
| |
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Category:Code Relief or Alternative
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Request for Alternative HNP-ISI-ALT-05-08 to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping for Hatch Unit 1 Plant Service Water
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Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1
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Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements
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Request for Alternative HNP-ISI-ALT-05-03, Version 1.0, Regarding Reactor Pressure Vessel Flange Leak-Off Piping
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Relief from the Requirements of the ASME Code
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Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1
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E.I Hatch, Units 1 and 2 - 10CFR 50.55a Request No. HNP-ISI-ALT-5-01, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Maintaining Isi/Cii Related Activities on the 2001 E/2003A ASME Section XI Code
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Safety Evaluation of Relief Request HNP-ISI-ALT-10, Version 1, for the Fourth 10-Year Inservice Inspection Interval Temporary Non-Code Repair of Service Water Piping, TAC ME4253
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Safety Evaluation for Alternative ISI-ALT-08
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Request for Relief from the Requirements of the American Society of Mechanical Engineered Boiler and Vessel Code (ASME Code)
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Request for Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)
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RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875)
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Fourth 10-Year Interval IST Program Update
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Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-38
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Safety Evaluation Re. Request to Use ASME Code Case N-661
NL-03-1744, Third 10-Year Interval Inservice Testing Program Submittal of Revised Relief Request RR-V-18 and Response to Request for Additional Information (RAI)2003-09-12012 September 2003
Third 10-Year Interval Inservice Testing Program Submittal of Revised Relief Request RR-V-18 and Response to Request for Additional Information (RAI)
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Relief Request, Third 10-year Inservice Inspection Program
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Relief Request, Third 10-Year Inservice Inspection Program
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Third 10-Year Interval Inservice Testing Program, Revision to Existing Relief Request RR-V-11
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2020-06-03
[Table view]
Category:Letter
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Request for Withholding Information from Public Disclosure License Amendment Request to Revise Technical Specification Surveillance Requirements to Increase Safety/Relief Valve Setpoints
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SLR Environmental Preapplication Meeting Summary
ML24303A4102024-10-17017 October 2024
Dir Results Letter to NRC - Hatch - Hurricane Helene
IR 05000321/20244012024-10-10010 October 2024
Security Baseline Inspection Report 05000321-2024401 and 05000366-2024401
ML24256A0282024-09-12012 September 2024
2024 Hatch Requal Inspection Corporate Notification Letter
NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024
Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024
Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024
0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc
IR 05000321/20240912024-08-27027 August 2024
NRC Investigation Report 2-2023-003 and NOV - NRC Inspection Report 05000321/2024091 and 05000366/2024091
IR 05000321/20240052024-08-26026 August 2024
Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Report 05000321/2024005 and 05000366/2024005
NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024
Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information
IR 05000321/20240022024-08-0808 August 2024
Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002
NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024
Response to Request for Additional Information Related to Request for Specific Exemption
NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024
Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components
NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024
10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023
ML24198A1252024-07-16016 July 2024
Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50
NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024
Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31
05000321/LER-2024-002-01, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024
Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications
05000321/LER-2024-003, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024
Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link
NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024
Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in
NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024
Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139
ML24163A0532024-06-14014 June 2024
Audit Plan - Alternative Seismic Method LAR
NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024
Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis
ML24149A0492024-06-0404 June 2024
SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program,
NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024
SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations
IR 05000321/20240902024-05-15015 May 2024
NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation
NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024
Annual Radiological Environmental Operating Reports for 2023
05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024
Manual Reactor Trip Due to Loss of Feedwater
NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.
NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024
Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5
IR 05000032/20240112024-04-25025 April 2024
Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011
NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024
Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023
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Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes
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Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications
IR 05000321/20240012024-04-22022 April 2024
Integrated Inspection Report 05000321/2024001 and 05000366/2024001
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Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint
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Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)
NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024
Response to Request for Additional Information Exemption Requests for Physical.
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Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.
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NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024
Correction of Technical Specification Omission
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[Table view]
Category:Safety Evaluation
MONTHYEARML23032A3322024-04-24024 April 2024
Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes
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Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
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Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program
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Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances)
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Issuance of Amendments Nos. 308 and 253, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements
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Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State
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Proposed Alternative HNP-ISI-ALT-05-04 for the Implementation of BWRVIP Guidelines
ML18320A0572018-11-30030 November 2018
Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure
ML18289A6192018-10-18018 October 2018
Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-07
ML18222A2962018-08-29029 August 2018
Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263)
ML18183A0732018-07-26026 July 2018
Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293)
ML18163A1602018-06-15015 June 2018
Proposed Alternative RR-V-11, Extension of Main Steam Safety Relief Valve Test Interval
ML18123A3682018-05-31031 May 2018
Issuance of Amendments to Adopt TSTF-542, RPV Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215)
ML18102B0162018-04-16016 April 2018
Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-05 (CAC Nos. MF9812 and MF9813; EPID L-2017-LLR-0053)
ML18022A1072018-01-25025 January 2018
Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059)
ML17355A4402018-01-22022 January 2018
Issuance of Amendments to Revise TS 3.6.4.1, Secondary Containment (CAC Nos. MF9590 and MF9591; EPID L-2017-LLA-0216)
ML17271A3072017-11-30030 November 2017
Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program
ML17279A0452017-10-26026 October 2017
Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements
ML17268A0442017-10-20020 October 2017
Relief Requests ISI RR 16, ISI-RR-17, ISI-44-21, and ISI-RR-22 for Relief from Inservice Inspection Requirements
2024-04-24
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January 3, 2006 Mr. H. L. Sumner, Jr.
Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE (CODE) (TAC NOS. MC6528 AND MC6529).
Dear Mr. Sumner:
By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted a proposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria from Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection interval.
The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1, Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensees proposed alternative provides an acceptable level of quality and safety. The NRC staff authorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch.
The NRC staff's safety evaluation is enclosed.
Sincerely,
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosure:
Safety Evaluation cc w/encl: See next page
January 3, 2006 Mr. H. L. Sumner, Jr.
Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS 1 AND 2 (HATCH), REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE (CODE) (TAC NOS. MC6528 AND MC6529).
Dear Mr. Sumner:
By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee), submitted a proposed request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the ASME Code requirements. Specifically, the licensee proposed using ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, qualified procedures and personnel, and the criteria from Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection interval.
The Nuclear Regulatory Commission (NRC) staff found the proposed alternative, ISI-ALT-1, Version 4.0, acceptable in accordance with 10 CFR 50.55a(a)(3)(I) because the licensees proposed alternative provides an acceptable level of quality and safety. The NRC staff authorizes the proposed alternative for the fourth 10-year inservice inspection interval for Hatch.
The NRC staff's safety evaluation is enclosed.
Sincerely,
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
Public RidsOgcRp LPL2-1Reading DNaujock RidsAcrsAcnwMailCenter RidsNrrLAMOBrien BWetzel, EDO RII RidsNrrPMGratton RidsAcrsRgn2MailCenter(MWidmann) RidsNrrDorlLplc(EMarinos) RidsNrrDciCpnb(TChan) RidsNrrDpr Accession No. ML053470091 NRR_028 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CPNB/BC OGC NRR/LPL2-1/BC NAME CGratton:kg MOBrien TChan S. Hamrick EMarinos DATE 12/22/05 01/03/06 SE dated 12/16/05 01/03/06 12/12/05 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST ISI-ALT-1, VERSION 4.0 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 (HATCH)
DOCKET NOS. 50-321 AND 50-366
1.0 INTRODUCTION
By letter dated March 30, 2005, as supplemented by letters dated August 3, October 5, and October 24, 2005, Southern Nuclear Operating Company, Inc. (the licensee) submitted a request for relief, ISI-ALT-1, for Hatch. The licensee proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code). Specifically, the licensee proposed using ASME Code,Section XI, Appendix VIII, Supplements 4 and 6 qualified procedures and personnel, and the criteria from the Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a that are applicable to the examination of the reactor pressure vessel (RPV) shell-to-flange and RPV head-to-flange welds. The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief request ISI-ALT-1. The request is for the fourth 10-year inservice inspection (ISI) interval which begins January 1, 2006, and ends December 31, 2015.
2.0 REGULATORY REQUIREMENTS The ISI of ASME Code Class 1, Class 2, and Class 3 components will be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Section 50.55a(a)(3) states in part that alternatives to the requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, Class 2, and Class 3 components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection 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 ISI 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. The ASME Code of record for Hatch for the fourth 10-year ISI interval is the 2001 edition through the 2003 addenda of the ASME Code. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
3.0 TECHNICAL EVALUATION
3.1 Component for Which Relief is Requested The applicable vessel welds are ASME Code Class 1, Category B-A pressure retaining welds in the RPV, Item No. B1.30, shell-to-flange weld, and Item No. B1.40, head-to-flange weld.
3.2 Applicable ASME Code Requirements The applicable requirement is the 2001 edition through the 2003 addenda of Section XI of the ASME Code, Appendix I, I-2120, which states that vessels greater than 2 inches in thickness shall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1.
3.3 Licensees Proposed Alternative The licensee proposed performing ultrasonic test (UT) examinations of the subject welds in accordance with the 2001 edition with the 2003 addenda of ASME Code,Section XI, with the modifications and limitations listed in the 10 CFR 50.55a. The licensee will use personnel and procedures qualified to the 2001 edition with no addenda,Section XI, Appendix VIII, Supplement 4, Qualification Requirements for the Clad/Base Metal Interface of Reactor Vessel, and Supplement 6, Qualification Requirements for Reactor Vessel Welds other than Clad/Base Metal Interface, as administered by the Energy Power Research Institute -
Performance Demonstration Initiative (PDI) Program.
3.4 Licensees Basis for Relief Appendix VIII requirements were developed with a rigorous, item-specific performance demonstration to ensure the effectiveness of UT examinations. The performance demonstration administered by PDI was conducted on RPV mockups containing flaws of various size and allocations. The demonstration established the capability of equipment, procedures, and personnel to find flaws that could be detrimental to the integrity of the RPV.
The performance demonstration showed that for the detection of flaws in RPV welds, the UT techniques were equal to or surpassed the requirements of the Section V, Article 4 of the ASME Code. Additionally, the PDI qualified sizing techniques are considered to be more accurate than the techniques used in Section V, Article 4.
Although Appendix VIII is not required for the RPV shell-to-flange and RPV head-to-flange welds, the use of Appendix VIII, Supplements 4 and 6 criteria for detection of flaws in these welds will be equal to or will exceed the requirements established by Section V, Article 4.
3.5 NRC Staff Evaluation The 2001 edition, 2003 addenda of ASME Code,Section XI, IWA-2232 states, Ultrasonic examination shall be conducted in accordance with Appendix I. Subarticle I-2120 states that vessels greater than 2 inches in thickness shall be examined in accordance with Section V, Article 4, as supplemented by Table I-2000-1.Section V, Article 4 provides a prescriptive-based process for qualifying UT of procedures and the scanning requirements for examinations. The prescriptive-based UT uses detailed criteria for setting up and calibrating equipment, calculating coverage, and detecting indications. The capability of a prescriptive-based UT examination is demonstrated with calibration blocks made from representative material containing holes and notches. Performance-based UT requires that detailed criteria be used for performance demonstration tests. The results for the tests are compared against statistically developed screening criteria. The tests are performed on representative mockups containing flaws similar to those found in operating plants. The performance-based tests demonstrate the effectiveness of UT personnel and procedures.
In lieu of Subarticle I-2120, the licensee proposed performing UT examinations of the subject welds in accordance with the 2001 edition, 2003 addenda of ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a. Section 50.55a limits the use of Appendix VIII to the 2001 edition with no addenda. Appendix VIII is a performance-based UT method. Examinations are performed with the scanning requirements for Supplements 4 and 6 that are provided in 10 CFR 50.55a(b)(2)(xv)(G), and the scanning volume identified in the ASME Code,Section XI, Figure IWB-2500-4 for the shell-to-flange weld and Figure IWB-2500-5 for the head-to-flange weld. The scanning requirements are: (1) for the examination of the inner 15 percent through-wall volume, scanning will be performed in four orthogonal directions to the maximum extent possible with procedures and personnel qualified to Appendix VIII, Supplement 4; (2) the remainder of the inner 15 percent through-wall volume is considered fully examined if coverage is obtained in at least one parallel and one perpendicular direction using personnel and procedures qualified for single side examination in accordance with Supplement 6; and (3) the remaining 85 percent through-wall volume is considered fully examined if coverage is obtained in one parallel and one perpendicular direction using procedures and personnel qualified for single side examination. Single side qualification criteria are provided in 10 CFR 50.55a(b)(2)(xv)(G)(2) and 10 CFR 50.55a(b)(2)(xvi).
The licensee will follow 10 CFR 50.55a(b)(2)(xv)(G) for the vessel-to-flange and head-to-flange welds. Because the head-to-flange weld has no cladding, the licensee will use Code Case N-664, Performance Demonstration Requirements for Examination of Unclad Reactor Pressure Vessel Welds, Excluding Flange Welds, that permits using Appendix VIII, Supplement 4 in lieu of the requirements of Appendix VIII, Supplement 6 for the inner 10 percent performance demonstration. Code Case N-664 is endorsed in Regulatory Guide, 1.147, Revision 14, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1. There are no specific performance demonstration requirements from 10 percent through 15 percent through-wall thickness. The scanning of the uncladded head-to-flange weld would be applied according to the requirements of 10 CFR 50.55a(b)(2)(xv)(G).
The procedures, equipment, and personnel qualified to Appendix VIII through the PDI program have shown a high probability of flaw detection, and have increased the reliability of
examinations of weld configurations within the scope of the PDI program. Therefore, the proposed alternative will provide an acceptable level of quality and safety.
4.0 Conclusion Based on the above evaluation, the NRC staff concludes that the licensees proposed alternative, ISI-ALT-1, Version 4.0, to use the 2001 edition of the ASME Code,Section XI, Appendix VIII, Supplements 4 and 6 as modified by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xvi) for the RPV shell-to-flange and head-to-flange welds will provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for Hatch for the fourth 10-year inservice inspection interval.
All other requirements of the ASME Code for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Donald Naujock, NRR Date: January 3, 2006
Edwin I. Hatch Nuclear Plant, Units 1 & 2 cc:
Laurence Bergen Chairman Oglethorpe Power Corporation Appling County Commissioners 2100 E. Exchange Place County Courthouse P.O. Box 1349 Baxley, GA 31513 Tucker, GA 30085-1349 Mr. Jeffrey T. Gasser Mr. R.D. Baker Executive Vice President Manager - Licensing Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. P.O. Box 1295 P.O. Box 1295 Birmingham, AL 35201-1295 Birmingham, AL 35201-1295 Mr. G. R. Frederick, General Manager Resident Inspector Edwin I. Hatch Nuclear Plant Plant Hatch Southern Nuclear Operating Company, Inc.
11030 Hatch Parkway N. U.S. Highway 1 North Baxley, GA 31531 P.O. Box 2010 Baxley, GA 31515 Harold Reheis, Director Department of Natural Resources Mr. K. Rosanski 205 Butler Street, SE., Suite 1252 Resident Manager Atlanta, GA 30334 Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant Steven M. Jackson P.O. Box 2010 Senior Engineer - Power Supply Baxley, GA 31515 Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334 Arthur H. Domby, Esq.
Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216
