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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 The letter dated October 24, 2005, included Version 4.0 of the relief request and superceded the letters dated March 30, August 3, and October 5, 2005, for relief requestISI-ALT-1.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
MONTHYEARML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19361A0562020-01-0909 January 2020 Proposed Alternative HNP-ISI-ALT-05-10 for the Implementation of BWRVIP 38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures NL-19-1336, Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures2019-11-0404 November 2019 Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures 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 NL-18-0713, 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 Water2018-05-17017 May 2018 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 NL-18-0408, Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing2018-04-0909 April 2018 Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing NL-18-0428, Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-12018-04-0909 April 2018 Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1 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 ML17205A3452017-08-10010 August 2017 Relief Request HNP-ISI-RR- 05-01 Regarding Reactor Pressure Vessel Head Stud Inservice Inspection Requirements ML17062A8322017-03-29029 March 2017 Relief Request ISI RR-15 Regarding Control Rod Drive Housing Welds Inservice Inspection Requirements ML16314A1322016-11-23023 November 2016 Request for Alternative HNP-ISI-ALT-05-03, Version 1.0, Regarding Reactor Pressure Vessel Flange Leak-Off Piping ML15310A4062015-12-30030 December 2015 Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval ML15352A2942015-12-28028 December 2015 Relief from the Requirements of the ASME Code ML15349A9732015-12-18018 December 2015 Relief from the Requirements of the ASME Code NL-15-1221, Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-12015-07-16016 July 2015 Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1 NL-15-1265, 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 Code2015-07-16016 July 2015 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 NL-15-1096, Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-06-18018 June 2015 Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-11-0162, Submittal of Revision to Relief Request RR-V-4 Fourth 10-Year Interval Inservice Testing Program2011-01-26026 January 2011 Submittal of Revision to Relief Request RR-V-4 Fourth 10-Year Interval Inservice Testing Program ML1100504942011-01-14014 January 2011 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 ML1020304442010-07-22022 July 2010 E-mail from Robert Martin, Regarding Verbal Authorixation of Relief - Note to File ML1020304522010-07-21021 July 2010 Verbal Authorization for Relief Request HNP-ISI-ALT-10 Temporary Non-code Repair of Service Water Piping ML1009802142010-04-0808 April 2010 Safety Evaluation of Relief Request HNP-ISI-ALT-09, Version 2.0, for the Fourth 10-year Inservice Inspection Interval ML0731301882007-12-0606 December 2007 Safety Evaluation for Alternative ISI-ALT-08 ML0713602972007-06-0505 June 2007 Relief, Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Request to Relief Nos. RR-42 Through RR-45, RR- 51, RR-58, RR-59, RR-60, & RR-62 ML0604502862006-02-14014 February 2006 Request for Relief from the Requirements of the American Society of Mechanical Engineered Boiler and Vessel Code (ASME Code) ML0534700912006-01-0303 January 2006 Relief, Boiler and Pressure Vessel Code, MC6528 and MC6529 ML0533303392005-12-22022 December 2005 Request for Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) ML0529700082005-11-0909 November 2005 Relief, Proposed Alternative RR-41 for Third and Fourth 10-Year Inservice Inspection Interval NL-05-1372, Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request2005-08-0202 August 2005 Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request ML0510301992005-04-25025 April 2005 RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875) NL-05-0726, Fourth 10-Year Interval IST Program Update2005-04-20020 April 2005 Fourth 10-Year Interval IST Program Update ML0501303172005-01-28028 January 2005 Ltr, RR No. 38 NL-04-1764, Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-382004-09-13013 September 2004 Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-38 ML0332800372003-11-21021 November 2003 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) ML0304100732003-02-10010 February 2003 Relief Request, Third 10-year Inservice Inspection Program ML0301404462003-01-14014 January 2003 Relief Request, Third 10-Year Inservice Inspection Program ML0230903232002-10-30030 October 2002 Third 10-Year Interval Inservice Testing Program, Revision to Existing Relief Request RR-V-11 ML0218305772002-07-0202 July 2002 Relief Requests for the Second 10-Year Inservice Inspection (ISI) Interval 2020-06-03
[Table view] Category:Letter
MONTHYEARIR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000321/20233012024-01-17017 January 2024 NRC Operator License Examination Report 05000321/2023301 and 05000366/2023301 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal IR 05000321/20230112023-11-17017 November 2023 Biennial Problem Identification and Resolution Inspection Report 050003212023011 and 050003662023011 ML23324A4472023-11-14014 November 2023 302 Exam Approval Letter IR 05000321/20230032023-11-0202 November 2023 Integrated Inspection Report 05000321/2023003, and 05000366/2023003 IR 05000321/20234032023-10-26026 October 2023 Cyber Security Inspection Report 05000321/2023403 and 05000366/2023403 IR 05000321/20234012023-10-17017 October 2023 Security Baseline Inspection Report 05000321 2023401 and 05000366 2023401 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report IR 05000321/20230052023-08-27027 August 2023 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 IR 05000321/20230022023-08-0808 August 2023 Integrated Inspection Report 07200036/2023001, 05000321/2023002, and 05000366/2023002 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 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 ML23201A0292023-07-20020 July 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement ML23178A0012023-06-27027 June 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000321 2023403 and 05000366 2023403 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use IR 05000321/20230102023-06-0909 June 2023 Focused Engineering Inspection Report 05000321 2023010 and 05000366 2023010 NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. ML23136B2942023-05-19019 May 2023 Summary of May 02, 2023, Observation Public Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a LAR for the Reactor Pressure Vessel Head Closure Bolts for Edwin I. Hatch Nuclear Plant, Units 1 and 2 NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 ML23123A2222023-05-0101 May 2023 Notification of Licensed Operator Initial Examination 05000321/2023301, and 05000366/2023301 IR 05000321/20230012023-04-26026 April 2023 Integrated Inspection Report 05000321/2023001 and 05000366/2023001 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal ML23065A1092023-03-0808 March 2023 Correction of Relief Request HNP-ISI-RR-05-02 Allowing to Continue Operation with a Flaw Indication on One Reactor Pressure Vessel Closure Bolt Until December 31, 2025 ML23053A2182023-03-0303 March 2023 Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program IR 05000321/20220062023-03-0101 March 2023 Annual Assessment Letter Edwin I. Hatch Nuclear Plant, Units 1 and 2 - NRC Inspection Report 05000321/2022006 and 05000366/2022006 NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23202A1122023-08-0202 August 2023 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 ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML22297A1462022-12-22022 December 2022 Issuance of Amendments Nos. 319 and 264, Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITS ML22293A0302022-11-0707 November 2022 Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227) ML22192A1172022-09-0202 September 2022 Issuance of Amendments Nos. 317 & 262, Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21264A6442021-09-24024 September 2021 Issuance of Amendment to Revise Technical Specification 3.7.2, Plant Service Water (Psw) System and Ultimate Heat Sink (UHS) (EPID L-2021-LLA-0164) (Emergency Circumstances) ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - 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[Table view] |
Text
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