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| | number = ML070440059 | | | number = ML070440059 |
| | issue date = 03/01/2007 | | | issue date = 03/01/2007 |
| | title = Request for Relief No. RR-ENG-2-45 for Remainder of Second 10-year Inservice Inspection Interval Use of Penetrameters in Radiography Examination (TAC Nos. MD3302 and MD3303) | | | title = Request for Relief No. RR-ENG-2-45 for Remainder of Second 10-year Inservice Inspection Interval Use of Penetrameters in Radiography Examination |
| | author name = Terao D | | | author name = Terao D |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
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| =Text= | | =Text= |
| {{#Wiki_filter:March 1, 2007Mr. James J. SheppardPresident and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483 | | {{#Wiki_filter:March 1, 2007 Mr. James J. Sheppard President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR RELIEFNO. RR-ENG-2-45 FOR REMAINDER OF SECOND 10-YEAR INSERVICE INSPECTION INTERVAL RE: USE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATION (TAC NOS. MD3302 AND MD3303) | | SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR RELIEF NO. RR-ENG-2-45 FOR REMAINDER OF SECOND 10-YEAR INSERVICE INSPECTION INTERVAL RE: USE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATION (TAC NOS. MD3302 AND MD3303) |
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| ==Dear Mr. Sheppard:== | | ==Dear Mr. Sheppard:== |
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| The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the informationprovided by South Texas Project Nuclear Operating Company (the licensee) in its letter dated June 14, 2006. The licensee requested the approval of Relief Request RR-ENG-2-45, for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, pertaining to examinations in conjunction with licensee's current second inservice inspection (ISI) interval. Specifically, the licensee requests use ofwire-type penetrameters for radiographic examinations as provided in ASME Code, Section III,1992 Edition with 1993 Addenda.Based on the information provided in the licensee's submittal, the NRC staff concludes that thelicensee has provided an acceptable alternative to the requirements of ASME Code in relief request RR-ENG-2-45. The NRC staff concludes that the alternative proposed by the licensee provides an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code ofFederal Regulations, paragraph 50.55a(a)(3)(i), the alternative is authorized for the STP, Units 1and 2, for the remainder of their second 10-year ISI interval.All other ASME Code, Section XI, requirements for which relief was not specifically requestedand authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. The NRC staff's safety evaluation is enclosed. Sincerely,/RA/David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-498 and 50-499 | | The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by South Texas Project Nuclear Operating Company (the licensee) in its letter dated June 14, 2006. The licensee requested the approval of Relief Request RR-ENG-2-45, for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, pertaining to examinations in conjunction with licensees current second inservice inspection (ISI) interval. Specifically, the licensee requests use of wire-type penetrameters for radiographic examinations as provided in ASME Code, Section III, 1992 Edition with 1993 Addenda. |
| | Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of ASME Code in relief request RR-ENG-2-45. The NRC staff concludes that the alternative proposed by the licensee provides an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code of Federal Regulations, paragraph 50.55a(a)(3)(i), the alternative is authorized for the STP, Units 1 and 2, for the remainder of their second 10-year ISI interval. |
| | All other ASME Code, Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. The NRC staffs safety evaluation is enclosed. |
| | Sincerely, |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc: See next page | | Safety Evaluation cc: See next page |
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| ML070440059*No significant change to SE input.OFFICENRR/LPL4/PMNRR/LPL4/LACNPB/BCOGC - NLONRR/LPL4/BCNAMEMThadaniLFeizollahiTChan*SHamrickDTerao DATE2/16/072/15/071/16/072/28/073/1/07 March 2007South Texas Project, Units 1 & 2 cc:Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 289 Wadsworth, TX 77483C. M. CanadyCity of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 J. J. Nesrsta/R. K. TempleE. Alercon/Kevin Pollo City Public Service Board P.O. Box 1771 San Antonio, TX 78296INPORecords Center 700 Galleria Parkway Atlanta, GA 30339-3064Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011Steve Winn/Christie JacobsEddy Daniels/Marty Ryan NRC Energy, Inc. | | ML070440059 *No significant change to SE input. |
| 211 Carnegie Center Princeton, NJ 08540Judge, Matagorda CountyMatagorda County Courthouse 1700 Seventh Street Bay City, TX 77414A. H. Gutterman, Esq.Morgan, Lewis & Bockius 1111 Pennsylvania Avenue, NW Washington, DC 20004E. D. HalpinSite Vice President STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483S. M. Head, Manager, LicensingSTP Nuclear Operating Company P.O. Box 289, Mail Code: N5014 Wadsworth, TX 77483C. T. BowmanGeneral Manager, Oversight STP Nuclear Operating Company P.O Box 389 Wadsworth, TX 77483Marilyn KistlerSr. Staff Specialist, Licensing STP Nuclear Operating Company P.O. Box 289, Mail Code 5014 Wadsworth, TX 77483Environmental and Natural ResourcesPolicy Director P.O. Box 12428 Austin, TX 78711-3189Jon C. WoodCox, Smith, & Matthews 112 East Pecan, Suite 1800 San Antonio, TX 78205DirectorDivision of Compliance & Inspection Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756 March 2007South Texas Project, Units 1 & 2 cc:Mr. Ted Enos 4200 South Hulen Suite 422 Ft. Worth, TX 76109Brian AlmonPublic Utility Commission William B. Travis Building P.O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326Susan M. JablonskiOffice of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087Mr. Glenn AdlerSenior Research Analyst Service Employees International Union 1313 L Street NW Washington, DC 20005Ken CoatesPlant General Manager STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483Mr. Terry Parks, Chief InspectorTexas Department of Licensing and Regulation Boiler Division P.O. Box 12157 Austin, TX 78711 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONUSE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATIONSTP NUCLEAR OPERATING COMPANYSOUTH TEXAS PROJECT, UNITS 1 AND 2DOCKET NOS. 50-498 AND 50-49
| | OFFICE NRR/LPL4/PM NRR/LPL4/LA CNPB/BC OGC - NLO NRR/LPL4/BC NAME MThadani LFeizollahi TChan* SHamrick DTerao DATE 2/16/07 2/15/07 1/16/07 2/28/07 3/1/07 South Texas Project, Units 1 & 2 cc: |
| | Senior Resident Inspector E. D. Halpin U.S. Nuclear Regulatory Commission Site Vice President P.O. Box 289 STP Nuclear Operating Company Wadsworth, TX 77483 South Texas Project Electric Generating Station C. M. Canady P.O. Box 289 City of Austin Wadsworth, TX 77483 Electric Utility Department 721 Barton Springs Road S. M. Head, Manager, Licensing Austin, TX 78704 STP Nuclear Operating Company P.O. Box 289, Mail Code: N5014 J. J. Nesrsta/R. K. Temple Wadsworth, TX 77483 E. Alercon/Kevin Pollo City Public Service Board C. T. Bowman P.O. Box 1771 General Manager, Oversight San Antonio, TX 78296 STP Nuclear Operating Company P.O Box 389 INPO Wadsworth, TX 77483 Records Center 700 Galleria Parkway Marilyn Kistler Atlanta, GA 30339-3064 Sr. Staff Specialist, Licensing STP Nuclear Operating Company Regional Administrator, Region IV P.O. Box 289, Mail Code 5014 U.S. Nuclear Regulatory Commission Wadsworth, TX 77483 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Environmental and Natural Resources Policy Director Steve Winn/Christie Jacobs P.O. Box 12428 Eddy Daniels/Marty Ryan Austin, TX 78711-3189 NRC Energy, Inc. |
| | 211 Carnegie Center Jon C. Wood Princeton, NJ 08540 Cox, Smith, & Matthews 112 East Pecan, Suite 1800 Judge, Matagorda County San Antonio, TX 78205 Matagorda County Courthouse 1700 Seventh Street Director Bay City, TX 77414 Division of Compliance & Inspection Bureau of Radiation Control A. H. Gutterman, Esq. Texas Department of State Health Services Morgan, Lewis & Bockius 1100 West 49th Street 1111 Pennsylvania Avenue, NW Austin, TX 78756 Washington, DC 20004 March 2007 |
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| ==91.0INTRODUCTION==
| | South Texas Project, Units 1 & 2 cc: |
| By letter dated June 14, 2006, South Texas Project Nuclear Operating Company (STPNOC, thelicensee) submitted relief request RR-ENG-2-45 for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Specifically the licensee requested the use of an alternative to the nondestructive examination requirements applicable to repairs of ASME Class 1, 2, and 3 pipe welds. The licensee requested the use of wire-type penetrameters, or IQIs [image quality indicators] for radiographic examination asrequired in the ASME Code, Section III, 1992 Edition with 1993 Addenda.
| | Mr. Ted Enos Ken Coates 4200 South Hulen Plant General Manager Suite 422 STP Nuclear Operating Company Ft. Worth, TX 76109 South Texas Project Electric Generating Station Brian Almon P.O. Box 289 Public Utility Commission Wadsworth, TX 77483 William B. Travis Building P.O. Box 13326 Mr. Terry Parks, Chief Inspector 1701 North Congress Avenue Texas Department of Licensing Austin, TX 78701-3326 and Regulation Boiler Division Susan M. Jablonski P.O. Box 12157 Office of Permitting, Remediation Austin, TX 78711 and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087 Mr. Glenn Adler Senior Research Analyst Service Employees International Union 1313 L Street NW Washington, DC 20005 March 2007 |
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| ==2.0REGULATORY EVALUATION==
| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION USE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATION STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 |
| Inservice Inspections (ISI) of ASME Code Class 1, 2 and 3 components shall be performed inaccordance with the requirements of Section XI of the ASME Code and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g), exceptwhere specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Paragraph 50.55a(a)(3) of 10 CFR 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, 2, 3 components (including supports)shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section XI, "Rules for Inservice Inspection (ISI) 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 testconducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subjectto the limitations and modifications listed therein. The code of record for STP, Units 1 and 2, is the 1992 Edition of the ASME Code.
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| ==3.0TECHNICAL EVALUATION== | | ==1.0 INTRODUCTION== |
| 3.1Component for which Relief is RequestedThe request for relief is applicable to ASME Code, Section XI, Class 1, 2, and 3 pipe welds.
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| 3.2ASME Code Requirements from which Relief is Requested (As Stated)As noted in IWA-4120, ASME Section XI, 1989 Edition:Repairs shall be performed in accordance with the Owner'sDesign Specification and the original Construction Code of the component or system. Later Editions and Addenda of the Construction Code or of Section III, either in their entirety orportions thereof, and Code Cases may be used. In accordance with the provisions of 10 CFR 50.55a(a)(3)(i), STPNOC has beenapproved to use a system leakage test to detect leakage from welded repairs, fabrication welds for replacement parts and piping subassemblies, and welds for installation of replacement items in accordance with Code Case N-416-2 as an alternative to system hydrostatic testing required by IWA-4700. For a system leakage test to be used, Code Case N-416-2 requires performance of non-destructive examination in accordance with the methods and acceptance criteria of the applicable Subsection of the 1992 Edition of ASME Code, Section III, no Addenda.ASME Section III, 1992 Edition includes the following:Paragraph NB-5111 (ASME Class 1)Radiographic examination shall be in accordance with Section V, Article 2,except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NB-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V] Table NB-5111-1 only refers to use of hole-type penetrameters; use of wire-typepenetrameters is not addressed.Paragraph NC-5111 (ASME Class 2) of ASME Section III, 1992 EditionRadiographic examination shall be in accordance with Section V, Article 2,except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NC-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V] Table NC-5111-1 only refers to use of hole-type penetrameters; use of wire-typepenetrameters is not addressed.3.3Proposed AlternativeUse of wire-type IQIs as incorporated into Tables NB-5111-1 (Class 1) and NC-5111-1(Class 2) in the 1993 Addenda of the 1992 Edition of the ASME Code, Section III. 3.4Licensee's Basis for Alternative (As Stated)Wire-type penetrameters provide the same function as hole-type penetrametersby indicating changes in thickness and spatial resolution of the image. The one-inch minimum length of the wire eliminates the problem of indicator loss due to distortion, anomalies, and part geometry that is commonly found with the target hole in plaque type penetrameters. For more complex configurations, wire-type penetrameters are superior in that placement is directly across the area of interest, encompassing the object's range of density and geometry without using shim blocks and pipe standards. Wire-type penetrameters have shown sensitivity equivalent to that of hole-typepenetrameters as documented in Table 4 of ASME Section V, Article 22, Standard SE-747. Because of its equivalent sensitivity, a wire-type penetrameter will provide results equivalent to those of a hole-type penetrameter. Therefore, the proposed alternative will maintain the quality of the examination results. Penetrameter requirements for performing radiography are specified by TablesNB-5111-1 (ASME Class 1) and NC-5111-1 (ASME Class 2) of ASME Section III, 1992 Edition. Based on these tables, only hole-type penetrameterscan be used. Wire-type penetrameters are not included in the 1992 Edition of
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| [ASME Code,] Section III. [In the 1992 Edition, 1993 Addenda] of ASME SectionIII, Tables NB-5111-1 and NC-5111-1 were revised to include wire-typepenetrameter requirements. The 1992 Edition with 1993 Addenda of ASME
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| [Code,] Section III, includes the provision for use of equivalent wire-type penetrameters, [and] is endorsed by the NRC in 10 CFR 50.55a. Consequently, as of the 1993 Addenda to [ASME C ode,] Section III. [The NRC staff hasdetermined that] wire-type penetrameters are acceptable for use when performing radiography.The proposed alternative to use wire-type image quality indicators forradiography examinations as provided for in ASME [Code,] Section III,1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. Therefore, STPNOC requests that application of the proposed alternative at the South Texas Project be authorized pursuant to 10 CFR 50.55a(a)(3)(i). 4.0EVALUATIONSTPNOC's use of a system leakage test in accordance with Code Case N-416-2; as analternative to system hydrostatic testing as required by IWA-4700, ASME Code, Section XI; has been approved by the NRC staff. Code Case 416-2 requires the licensee to perform non-destructive examinations in accordance with the methods and acceptance criteria of the 1992 Edition of the ASME Code, Section III, no Addenda. The applicable subsections areNB-5111 and NC-5111, and Tables NB-5111-1 and NC-5111-1. Wire-type IQIs were notincluded in the ASME Code, Section III, until the 1992 Edition with 1993 Addenda. The 1992Edition with 1993 Addenda of the ASME Code has been endorsed by the NRC in 10 CFR 50.55a, including the use of wire type IQIs.Volume 17 of the Ninth Edition of the American Society of Materials (ASM) Handbook Series,published in 1989, states that wire-type penetrameters are widely used in Europe, and a standard design is used in the United Kingdom, Germany, the Netherlands, and Scandinavia.
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| The International Organization for Standardization and the International Institute of Welding have also adopted the wide use of wire-type penetrameters. Also, the handbook states that wire-type penetrameters specified in the American Society for Testing and Materials (ASTM) standard E 747-87 are widely used in the United States. The specifications in the handbook were developed in a public forum, and with public consensus. The ASTM Standard E 747-87 referenced in the ASM Handbook is identical to the 1989 Edition of ASME's Standard SE-747-87.Based on its previous endorsement of the1992 Edition with 1993 Addenda of the ASME Code,and the widespread use of wire-type penetrameters in industry, the NRC staff has determined that the wire-type penetrameters listed in Table NB-5111-1 (NC-5111-1) to the 1992 Edition with 1993 Addenda of the ASME Code will provide comparable density measurements; and, therefore, will provide an acceptable level of quality and safety.
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| ==5.0CONCLUSION== | | By letter dated June 14, 2006, South Texas Project Nuclear Operating Company (STPNOC, the licensee) submitted relief request RR-ENG-2-45 for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Specifically the licensee requested the use of an alternative to the nondestructive examination requirements applicable to repairs of ASME Class 1, 2, and 3 pipe welds. The licensee requested the use of wire-type penetrameters, or IQIs [image quality indicators] for radiographic examination as required in the ASME Code, Section III, 1992 Edition with 1993 Addenda. |
| Based on the above evaluation, the NRC staff concludes that the proposed alternative to use wire-type IQIs for radiography examinations as provided for in ASME Code, Section III,1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. Pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the STPNOC to use the proposedalternative for the duration of the second 10-year ISI interval at South Texas Project, Units 1 and 2. All other ASME Code, Section XI, requirements for which relief was not specifically requestedand authorized herein by the NRC staff remain applicable including third-party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: Isaac A. Anchondo Date: March 1, 2007}} | | |
| | ==2.0 REGULATORY EVALUATION== |
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| | Inservice Inspections (ISI) of ASME Code Class 1, 2 and 3 components shall be performed in accordance with the requirements of Section XI of the ASME Code and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (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). Paragraph 50.55a(a)(3) of 10 CFR 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, 2, 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section XI, Rules for Inservice Inspection (ISI) 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 test conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated |
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| | by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The code of record for STP, Units 1 and 2, is the 1992 Edition of the ASME Code. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | 3.1 Component for which Relief is Requested The request for relief is applicable to ASME Code, Section XI, Class 1, 2, and 3 pipe welds. |
| | 3.2 ASME Code Requirements from which Relief is Requested (As Stated) |
| | As noted in IWA-4120, ASME Section XI, 1989 Edition: |
| | Repairs shall be performed in accordance with the Owner's Design Specification and the original Construction Code of the component or system. Later Editions and Addenda of the Construction Code or of Section III, either in their entirety or portions thereof, and Code Cases may be used. |
| | In accordance with the provisions of 10 CFR 50.55a(a)(3)(i), STPNOC has been approved to use a system leakage test to detect leakage from welded repairs, fabrication welds for replacement parts and piping subassemblies, and welds for installation of replacement items in accordance with Code Case N-416-2 as an alternative to system hydrostatic testing required by IWA-4700. For a system leakage test to be used, Code Case N-416-2 requires performance of non-destructive examination in accordance with the methods and acceptance criteria of the applicable Subsection of the 1992 Edition of ASME Code, Section III, no Addenda. |
| | ASME Section III, 1992 Edition includes the following: |
| | Paragraph NB-5111 (ASME Class 1) |
| | Radiographic examination shall be in accordance with Section V, Article 2, except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NB-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V] |
| | Table NB-5111-1 only refers to use of hole-type penetrameters; use of wire-type penetrameters is not addressed. |
| | Paragraph NC-5111 (ASME Class 2) of ASME Section III, 1992 Edition Radiographic examination shall be in accordance with Section V, Article 2, except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NC-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V] |
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| | Table NC-5111-1 only refers to use of hole-type penetrameters; use of wire-type penetrameters is not addressed. |
| | 3.3 Proposed Alternative Use of wire-type IQIs as incorporated into Tables NB-5111-1 (Class 1) and NC-5111-1 (Class 2) in the 1993 Addenda of the 1992 Edition of the ASME Code, Section III. |
| | 3.4 Licensees Basis for Alternative (As Stated) |
| | Wire-type penetrameters provide the same function as hole-type penetrameters by indicating changes in thickness and spatial resolution of the image. The one-inch minimum length of the wire eliminates the problem of indicator loss due to distortion, anomalies, and part geometry that is commonly found with the target hole in plaque type penetrameters. For more complex configurations, wire-type penetrameters are superior in that placement is directly across the area of interest, encompassing the object's range of density and geometry without using shim blocks and pipe standards. |
| | Wire-type penetrameters have shown sensitivity equivalent to that of hole-type penetrameters as documented in Table 4 of ASME Section V, Article 22, Standard SE-747. Because of its equivalent sensitivity, a wire-type penetrameter will provide results equivalent to those of a hole-type penetrameter. Therefore, the proposed alternative will maintain the quality of the examination results. |
| | Penetrameter requirements for performing radiography are specified by Tables NB-5111-1 (ASME Class 1) and NC-5111-1 (ASME Class 2) of ASME Section III, 1992 Edition. Based on these tables, only hole-type penetrameters can be used. Wire-type penetrameters are not included in the 1992 Edition of |
| | [ASME Code,] Section III. [In the 1992 Edition, 1993 Addenda] of ASME Section III, Tables NB-5111-1 and NC-5111-1 were revised to include wire-type penetrameter requirements. The 1992 Edition with 1993 Addenda of ASME |
| | [Code,] Section III, includes the provision for use of equivalent wire-type penetrameters, [and] is endorsed by the NRC in 10 CFR 50.55a. Consequently, as of the 1993 Addenda to [ASME Code,] Section III. [The NRC staff has determined that] wire-type penetrameters are acceptable for use when performing radiography. |
| | The proposed alternative to use wire-type image quality indicators for radiography examinations as provided for in ASME [Code,] Section III, 1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. Therefore, STPNOC requests that application of the proposed alternative at the South Texas Project be authorized pursuant to 10 CFR 50.55a(a)(3)(i). |
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| | 4.0 EVALUATION STPNOCs use of a system leakage test in accordance with Code Case N-416-2; as an alternative to system hydrostatic testing as required by IWA-4700, ASME Code, Section XI; has been approved by the NRC staff. Code Case 416-2 requires the licensee to perform non-destructive examinations in accordance with the methods and acceptance criteria of the 1992 Edition of the ASME Code, Section III, no Addenda. The applicable subsections are NB-5111 and NC-5111, and Tables NB-5111-1 and NC-5111-1. Wire-type IQIs were not included in the ASME Code, Section III, until the 1992 Edition with 1993 Addenda. The 1992 Edition with 1993 Addenda of the ASME Code has been endorsed by the NRC in 10 CFR 50.55a, including the use of wire type IQIs. |
| | Volume 17 of the Ninth Edition of the American Society of Materials (ASM) Handbook Series, published in 1989, states that wire-type penetrameters are widely used in Europe, and a standard design is used in the United Kingdom, Germany, the Netherlands, and Scandinavia. |
| | The International Organization for Standardization and the International Institute of Welding have also adopted the wide use of wire-type penetrameters. Also, the handbook states that wire-type penetrameters specified in the American Society for Testing and Materials (ASTM) standard E 747-87 are widely used in the United States. The specifications in the handbook were developed in a public forum, and with public consensus. The ASTM Standard E 747-87 referenced in the ASM Handbook is identical to the 1989 Edition of ASMEs Standard SE-747-87. |
| | Based on its previous endorsement of the1992 Edition with 1993 Addenda of the ASME Code, and the widespread use of wire-type penetrameters in industry, the NRC staff has determined that the wire-type penetrameters listed in Table NB-5111-1 (NC-5111-1) to the 1992 Edition with 1993 Addenda of the ASME Code will provide comparable density measurements; and, therefore, will provide an acceptable level of quality and safety. |
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| | ==5.0 CONCLUSION== |
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| | Based on the above evaluation, the NRC staff concludes that the proposed alternative to use wire-type IQIs for radiography examinations as provided for in ASME Code, Section III, 1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. |
| | Pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the STPNOC to use the proposed alternative for the duration of the second 10-year ISI interval at South Texas Project, Units 1 and 2. |
| | All other ASME Code, Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable including third-party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: Isaac A. Anchondo Date: March 1, 2007}} |
Letter Sequence Other |
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MONTHYEARML0704602432007-02-23023 February 2007
Ltr Request for Additional Information Related to the Request for Extended Power Uprate
Project stage: RAI
ML0704400592007-03-0101 March 2007
Request for Relief No. RR-ENG-2-45 for Remainder of Second 10-year Inservice Inspection Interval Use of Penetrameters in Radiography Examination
Project stage: Other
2007-02-23
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML24201A0462024-07-26026 July 2024
Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-07
ML24040A1962024-02-13013 February 2024
Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-06
ML22245A0012022-09-12012 September 2022
Relief from the Requirements of the ASME Code
ML20227A3852020-09-0303 September 2020
Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping
NOC-AE-20003702, Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-03)2020-01-22022 January 2020
Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-03)
ML19142A3072019-08-13013 August 2019
Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles
NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23)2019-02-28028 February 2019
Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23)
ML18303A2062018-11-0707 November 2018
Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations
NOC-AE-18003598, Response to Request for Additional Information Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)2018-09-26026 September 2018
Response to Request for Additional Information Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)
ML18177A4252018-07-24024 July 2018
Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval
ML18187A1492018-07-24024 July 2018
Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
NOC-AE-18003578, Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)2018-06-25025 June 2018
Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)
NOC-AE-18003547, Proposed Alternative to Reactor Vessel Inservice Inspection Intervals (Relief Request RR-ENG-3-14)2018-02-15015 February 2018
Proposed Alternative to Reactor Vessel Inservice Inspection Intervals (Relief Request RR-ENG-3-14)
ML16174A0912016-06-30030 June 2016
Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval
ML15218A3672015-08-21021 August 2015
Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval
ML13102A1262013-04-23023 April 2013
Withdrawal of Relief Request RR-ENG-3-12 from ASME Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valve with Seal Cap, Third 10-year Inservice Inspection Interval
ML13087A5172013-04-12012 April 2013
Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage
ML13004A3392013-03-12012 March 2013
Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval
NOC-AE-12002939, Request for Relief from ASME Section XI Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valves with Seal Cap Enclosures (Relief Request RR-ENG-3-12)2013-02-0707 February 2013
Request for Relief from ASME Section XI Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valves with Seal Cap Enclosures (Relief Request RR-ENG-3-12)
NOC-AE-12002956, Response to Request for Additional Information Regarding Relief Request RR-ENG-3-09 for the Essential Cooling Water System2013-01-31031 January 2013
Response to Request for Additional Information Regarding Relief Request RR-ENG-3-09 for the Essential Cooling Water System
ML12243A3432012-09-10010 September 2012
RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds
ML12235A3472012-08-28028 August 2012
Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054)
ML12201A2562012-08-16016 August 2012
Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012
NOC-AE-12002837, Response to Request for Additional Information: Application of an Alternative to Requirements for Examination of Class 1 and Class 2 Piping Welds (Relief Request RR-ENG-3-04)2012-05-0909 May 2012
Response to Request for Additional Information: Application of an Alternative to Requirements for Examination of Class 1 and Class 2 Piping Welds (Relief Request RR-ENG-3-04)
NOC-AE-12002807, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-3-08)2012-03-12012 March 2012
Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-3-08)
ML1118605352011-07-29029 July 2011
Relief Request RR-ENG-2-55 from ASME Code Requirements for Weld Examinations, Second 10-Year Inservice Inspection Interval
ML1109803472011-04-20020 April 2011
Relief Request RR-ENG-3-01, from ASME Code Requirements for Steam Generator Main Steam Nozzle Non-Destructive Examination, Third 10-Year Inservice Inspection Interval
ML1108109482011-04-0707 April 2011
Request for Relief RR-ENG-3-03 from ASME Code Requirements for Pump Casing Inservice Inspection Examination, Third 10-Year Inservice Inspection Interval
ML1108400762011-04-0505 April 2011
Request for Relief RR-ENG-3-02 from ASME Code Requirements for Reactor Pressure Vessel Flange Insert Non-Destructive Examination, Third 10-Year Inservice Inspection Interval
NOC-AE-10002600, Request for Relief from ASME Section XI Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds (RR-ENG-3-05)2010-10-18018 October 2010
Request for Relief from ASME Section XI Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds (RR-ENG-3-05)
NOC-AE-10002594, Request for Relief from ASME Section XI Code Requirements for Pump Casing Inservice Inspection Examination (Relief Request RR-ENG-3-03)2010-09-20020 September 2010
Request for Relief from ASME Section XI Code Requirements for Pump Casing Inservice Inspection Examination (Relief Request RR-ENG-3-03)
ML1021500772010-09-0202 September 2010
Relief Request Nos. VRR-01, PRR-03, PRR-02, and PRR-01 for Third 10-year Interval Inservice Testing Program for Pumps and Valves (TAC Nos. ME3515 Through ME3522)
ML1006208692010-03-24024 March 2010
Authorization of Relief Request RR-ENG-2-53, Alternative to Inservice Inspection Requirements for Ultrasonic Exam of Reactor Pressure Vessel Shell-to-Flange Weld
ML1005395882010-03-12012 March 2010
Relief Request RR-ENG-2-52 from ASME Code, Section XI Requirements for Essential Cooling Water System Code Repair
NOC-AE-09002399, Request for Relief from ASME Boiler and Pressure Vessel Code Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-2-52)2009-03-12012 March 2009
Request for Relief from ASME Boiler and Pressure Vessel Code Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-2-52)
ML0827502202008-12-0909 December 2008
Relief Request RR-ENG-2-30, Request for Relief to Use ASME Code Case N-516-3, Underwater Welding, Section XI, Division 1
ML0827707852008-11-12012 November 2008
Authorization of Relief Request RR-ENG-2-51 from ASME Code Case N-498-4, on 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems
ML0824901602008-09-26026 September 2008
Relief Request RR-ENG-2-49, Second 10-Year Inservice Inspection Interval, Deferral of Code Repair in the Essential Cooling Water System Piping
ML0735410722008-01-10010 January 2008
Request for Relief No. RR-ENG-2-48 from ASME Code Case N-638-1 Requirements Regarding Start Time for 48-Hour Hold Period Before Non-Destructive Examination of Weld Overlay Repair
ML0731204462007-11-30030 November 2007
Relief Request RR-ENG-2-47 for Approval of Temporary Non-code Repair and Deferral of Code Repair Upgraded Essential Cooling Water System Piping
NOC-AE-07002211, Relief Request (RR-ENG-2-50) for the Second 10 Year ISI Interval from 10 CFR 50.55a for the Purpose of Invoking Code Case N-698, Design Stress Intensities and Yield Strength Values For...2007-10-0202 October 2007
Relief Request (RR-ENG-2-50) for the Second 10 Year ISI Interval from 10 CFR 50.55a for the Purpose of Invoking Code Case N-698, Design Stress Intensities and Yield Strength Values For...
ML0708510082007-04-30030 April 2007
Relief Request No. RR-ENG-2-44 on Deferral of Code Repair of Essential Cooling Water System Indication
ML0708102642007-04-0202 April 2007
Relief, Request for Relief No. RR-ENG-2-43 for Remainder of Second 10-year Inservice Inspection Interval Application of Weld Overlays in Pressurizer Nozzle Safe End Welds (TAC Nos. MD1414 - MD1423)
ML0706500752007-03-15015 March 2007
Request to Use 2001 Edition Through 2003 Addenda of ASME Code for Operations and Maintenance for Remainder of Second 10-Year Inservice Testing Program Interval
ML0704400592007-03-0101 March 2007
Request for Relief No. RR-ENG-2-45 for Remainder of Second 10-year Inservice Inspection Interval Use of Penetrameters in Radiography Examination
ML0622303092006-10-26026 October 2006
Response to Relief Request RR-ENG-2-42 for Approval Non-Code Repair and Deferral of Code Repair of Essential Cooling Water System Piping, TAC MC8804
NOC-AE-06002031, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations2006-06-14014 June 2006
Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations
ML0610907542006-05-25025 May 2006
Relief, Relief Request RR-ENG-2-39 and RR-ENG-2-40 for Approval of Temporary Non-code Repair and Deferral of Code Repair of Essential Cooling Water System Piping, Trains 1B and 1C
ML0609702402006-05-12012 May 2006
Relief, RR-ENG-2-41 TAC No. MC8279
NOC-AE-05001899, Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for the Essential Cooling Water System (Ecw Train 1 C) (Relief Request RR-ENG-2-40)2005-07-19019 July 2005
Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for the Essential Cooling Water System (Ecw Train 1 C) (Relief Request RR-ENG-2-40)
2024-07-26
[Table view]
Category:Letter
MONTHYEARIR 05000498/20244022024-10-23023 October 2024
Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402
05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024
Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function
ML24295A0772024-10-21021 October 2024
Licensed Operator Positive Fitness-for-Duty Test
05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024
Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
NOC-AE-240040, Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2024-10-16016 October 2024
Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan
IR 05000498/20243012024-10-0707 October 2024
NRC Examination Report 05000498/2024301 and 05000499/2024301
ML24255A0322024-09-30030 September 2024
The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter
ML24269A1762024-09-25025 September 2024
Tpdes Permit Renewal Application WQ0001 908000
05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024
Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps
ML24271A3022024-09-18018 September 2024
STP-2024-09 Post-Exam Comments - Redacted
ML24274A0902024-09-16016 September 2024
Written Response - EA-24-026 STP Operator - Redacted
ML24250A1882024-09-11011 September 2024
Request for Information for an NRC Post-Approval Site Inspection for License Renewal
ML24249A3372024-09-0404 September 2024
Inservice Inspection Summary Report - 2RE23
05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024
Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
ML24234A0912024-08-27027 August 2024
NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301
IR 05000498/20240052024-08-22022 August 2024
Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005)
IR 05000498/20240022024-08-0909 August 2024
Integrated Inspection Report 05000498/2024002 and 05000499/2024002
IR 05000498/20240102024-08-0808 August 2024
Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010
ML24213A0842024-07-31031 July 2024
Application for Order Consenting to Direct Transfer of Licenses
ML24218A1462024-07-26026 July 2024
2. EPA Comments on South Texas Project Exemption Ea/Fonsi
ML24207A1782024-07-25025 July 2024
Licensed Operator Positive Fitness-For-Duty Test
05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024
Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024
Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump
05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024
Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024
Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
IR 05000498/20244042024-06-0303 June 2024
Cyber Security Inspection Report 05000498/2024404 (Cover Letter)
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24136A2872024-05-15015 May 2024
Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual
ML24136A2842024-05-15015 May 2024
Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance
ML24137A0882024-05-15015 May 2024
Operator Licensinq Examination Schedule Revision 3
ML24130A2712024-05-0909 May 2024
Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24128A1572024-05-0707 May 2024
Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance
IR 05000498/20240012024-05-0606 May 2024
Integrated Inspection Report 05000498/2024001 & 05000499/2024001
ML24120A3762024-04-29029 April 2024
Annual Dose Report for 2023
ML24116A2282024-04-25025 April 2024
Annual Environmental Operating Report
05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024
Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water
ML24116A3032024-04-25025 April 2024
Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment
ML24117A1602024-04-24024 April 2024
2023 Radioactive Effluent Release Report
ML24102A2452024-04-23023 April 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24113A3122024-04-22022 April 2024
Cycle 24 Core Operating Limits Report
ML24097A0072024-04-0606 April 2024
Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75
ML24092A1902024-04-0101 April 2024
Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24088A3022024-03-28028 March 2024
Financial Assurance for Decommissioning - 2024 Update
ML24081A3972024-03-21021 March 2024
Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML24080A2902024-03-19019 March 2024
Nuclear Liability Certificates of Insurance
ML24066A2002024-03-0606 March 2024
10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes
ML24079A1312024-03-0505 March 2024
Nuclear Insurance Protection
ML24060A1742024-02-28028 February 2024
Submittal of Annual Fitness for Duty Performance Report for 2023
IR 05000498/20230062024-02-28028 February 2024
Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006)
IR 05000498/20240132024-02-27027 February 2024
Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013
2024-09-04
[Table view]
Category:Safety Evaluation
MONTHYEARML24201A0462024-07-26026 July 2024
Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-07
ML24022A2252024-02-20020 February 2024
Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation
ML23279A0342023-10-30030 October 2023
Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter)
ML23279A0482023-10-30030 October 2023
Associated Independent Spent Fuel Storage Installation - Enclosure 4 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Nonproprietary Safety Evaluation)
ML23015A0012023-02-0606 February 2023
Issuance of Amendment Nos. 225 and 210 to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
ML22300A2492022-12-0606 December 2022
Approval for Alternate Disposal Procedures for Very Low-Level Radioactive Material (EPID: L?2021?LLL?0022)
ML22245A0012022-09-12012 September 2022
Relief from the Requirements of the ASME Code
ML21319A3552021-12-0909 December 2021
Issuance of Amendment Nos. 224 and 209 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML21320A0022021-12-0808 December 2021
Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index
NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 22021-05-11011 May 2021
Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2
ML21033A2392021-04-0808 April 2021
Issuance of Amendment Nos. 222 and 207 to Revise Technical Specifications to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil
ML20253A0462020-09-29029 September 2020
Issuance of Amendment Nos. 220 and 205 to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec
ML20227A3852020-09-0303 September 2020
Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping
ML20199M1622020-07-21021 July 2020
Proposed Alternatives PRR-01, PRR-02, PRR-03, and PRR-04 to the Requirements of the ASME OM Code (Epids L-2020-LLR-0007 to L-2020-LLR-0010)
ML20141L6122020-05-28028 May 2020
Issuance of Amendment No. 219 to Revise Technical Specifications to Reduce Safety Injection Accumulators Minimum Pressures (Exigent Circumstances)
ML19322A7192019-12-0909 December 2019
Issuance of Amendment Nos. 218 and 204 to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules
ML19217A0602019-10-24024 October 2019
Issuance of Amendment Nos. 217 and 203 Revision to Technical Specification Tables to Change Terminology for the P-13 Permissive Interlock Description
ML19213A1472019-08-20020 August 2019
Issuance of Amendment Nos. 216 and 202 Standby Diesel Generator Surveillance Requirements
ML19142A3072019-08-13013 August 2019
Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles
ML19067A2222019-06-0606 June 2019
Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month
ML18303A2062018-11-0707 November 2018
Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations
ML18187A1492018-07-24024 July 2018
Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
ML18177A4252018-07-24024 July 2018
Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval
ML18159A2122018-07-19019 July 2018
Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265)
ML18128A3422018-06-0707 June 2018
Issuance of Amendment Nos. 213 and 199 to Revise TSs for Administrative Changes and to Relocate Fxy Exclusion Zones to the Colrs(Cac Nos. MG0253 and MG0254, EPID-L-2017-LLA-0300)
ML17019A0022017-07-11011 July 2017
Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191
ML17038A2232017-07-11011 July 2017
Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191
ML16319A0102016-12-21021 December 2016
Issuance of Amendment No. 211, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16174A0912016-06-30030 June 2016
Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval
ML16116A0072016-04-29029 April 2016
Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years
ML15342A0032015-12-28028 December 2015
Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179)
ML15343A1282015-12-11011 December 2015
Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances)
ML15209A6412015-09-22022 September 2015
Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169
ML15218A3672015-08-21021 August 2015
Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval
ML15201A1952015-08-20020 August 2015
Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6
ML15075A1462015-04-29029 April 2015
Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times
ML15049A1292015-02-27027 February 2015
Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits
ML14339A1702015-02-13013 February 2015
Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability
ML14281A0652015-01-29029 January 2015
Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date
ML13221A0042013-09-0909 September 2013
Issuance of Amendment Nos. 201 and 189, Revise TS 5.0, Design Features, to Reflect Removal of Visitor'S Center Building and References to Emergency Operations Facility
ML13142A1602013-06-0606 June 2013
Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment
ML13008A5282013-04-25025 April 2013
Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
ML13087A5172013-04-12012 April 2013
Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage
ML13004A3392013-03-12012 March 2013
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March 1, 2007 Mr. James J. Sheppard President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR RELIEF NO. RR-ENG-2-45 FOR REMAINDER OF SECOND 10-YEAR INSERVICE INSPECTION INTERVAL RE: USE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATION (TAC NOS. MD3302 AND MD3303)
Dear Mr. Sheppard:
The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by South Texas Project Nuclear Operating Company (the licensee) in its letter dated June 14, 2006. The licensee requested the approval of Relief Request RR-ENG-2-45, for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, pertaining to examinations in conjunction with licensees current second inservice inspection (ISI) interval. Specifically, the licensee requests use of wire-type penetrameters for radiographic examinations as provided in ASME Code,Section III, 1992 Edition with 1993 Addenda.
Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of ASME Code in relief request RR-ENG-2-45. The NRC staff concludes that the alternative proposed by the licensee provides an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code of Federal Regulations, paragraph 50.55a(a)(3)(i), the alternative is authorized for the STP, Units 1 and 2, for the remainder of their second 10-year ISI interval.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. The NRC staffs safety evaluation is enclosed.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Safety Evaluation cc: See next page
ML070440059 *No significant change to SE input.
OFFICE NRR/LPL4/PM NRR/LPL4/LA CNPB/BC OGC - NLO NRR/LPL4/BC NAME MThadani LFeizollahi TChan* SHamrick DTerao DATE 2/16/07 2/15/07 1/16/07 2/28/07 3/1/07 South Texas Project, Units 1 & 2 cc:
Senior Resident Inspector E. D. Halpin U.S. Nuclear Regulatory Commission Site Vice President P.O. Box 289 STP Nuclear Operating Company Wadsworth, TX 77483 South Texas Project Electric Generating Station C. M. Canady P.O. Box 289 City of Austin Wadsworth, TX 77483 Electric Utility Department 721 Barton Springs Road S. M. Head, Manager, Licensing Austin, TX 78704 STP Nuclear Operating Company P.O. Box 289, Mail Code: N5014 J. J. Nesrsta/R. K. Temple Wadsworth, TX 77483 E. Alercon/Kevin Pollo City Public Service Board C. T. Bowman P.O. Box 1771 General Manager, Oversight San Antonio, TX 78296 STP Nuclear Operating Company P.O Box 389 INPO Wadsworth, TX 77483 Records Center 700 Galleria Parkway Marilyn Kistler Atlanta, GA 30339-3064 Sr. Staff Specialist, Licensing STP Nuclear Operating Company Regional Administrator, Region IV P.O. Box 289, Mail Code 5014 U.S. Nuclear Regulatory Commission Wadsworth, TX 77483 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Environmental and Natural Resources Policy Director Steve Winn/Christie Jacobs P.O. Box 12428 Eddy Daniels/Marty Ryan Austin, TX 78711-3189 NRC Energy, Inc.
211 Carnegie Center Jon C. Wood Princeton, NJ 08540 Cox, Smith, & Matthews 112 East Pecan, Suite 1800 Judge, Matagorda County San Antonio, TX 78205 Matagorda County Courthouse 1700 Seventh Street Director Bay City, TX 77414 Division of Compliance & Inspection Bureau of Radiation Control A. H. Gutterman, Esq. Texas Department of State Health Services Morgan, Lewis & Bockius 1100 West 49th Street 1111 Pennsylvania Avenue, NW Austin, TX 78756 Washington, DC 20004 March 2007
South Texas Project, Units 1 & 2 cc:
Mr. Ted Enos Ken Coates 4200 South Hulen Plant General Manager Suite 422 STP Nuclear Operating Company Ft. Worth, TX 76109 South Texas Project Electric Generating Station Brian Almon P.O. Box 289 Public Utility Commission Wadsworth, TX 77483 William B. Travis Building P.O. Box 13326 Mr. Terry Parks, Chief Inspector 1701 North Congress Avenue Texas Department of Licensing Austin, TX 78701-3326 and Regulation Boiler Division Susan M. Jablonski P.O. Box 12157 Office of Permitting, Remediation Austin, TX 78711 and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087 Mr. Glenn Adler Senior Research Analyst Service Employees International Union 1313 L Street NW Washington, DC 20005 March 2007
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION USE OF PENETRAMETERS IN RADIOGRAPHIC EXAMINATION STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated June 14, 2006, South Texas Project Nuclear Operating Company (STPNOC, the licensee) submitted relief request RR-ENG-2-45 for South Texas Project (STP), Units 1 and 2, in which the licensee requested relief from certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Specifically the licensee requested the use of an alternative to the nondestructive examination requirements applicable to repairs of ASME Class 1, 2, and 3 pipe welds. The licensee requested the use of wire-type penetrameters, or IQIs [image quality indicators] for radiographic examination as required in the ASME Code,Section III, 1992 Edition with 1993 Addenda.
2.0 REGULATORY EVALUATION
Inservice Inspections (ISI) of ASME Code Class 1, 2 and 3 components shall be performed in accordance with the requirements of Section XI of the ASME Code and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (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). Paragraph 50.55a(a)(3) of 10 CFR 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, 2, 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection (ISI) 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 test conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated
by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The code of record for STP, Units 1 and 2, is the 1992 Edition of the ASME Code.
3.0 TECHNICAL EVALUATION
3.1 Component for which Relief is Requested The request for relief is applicable to ASME Code,Section XI, Class 1, 2, and 3 pipe welds.
3.2 ASME Code Requirements from which Relief is Requested (As Stated)
As noted in IWA-4120, ASME Section XI, 1989 Edition:
Repairs shall be performed in accordance with the Owner's Design Specification and the original Construction Code of the component or system. Later Editions and Addenda of the Construction Code or of Section III, either in their entirety or portions thereof, and Code Cases may be used.
In accordance with the provisions of 10 CFR 50.55a(a)(3)(i), STPNOC has been approved to use a system leakage test to detect leakage from welded repairs, fabrication welds for replacement parts and piping subassemblies, and welds for installation of replacement items in accordance with Code Case N-416-2 as an alternative to system hydrostatic testing required by IWA-4700. For a system leakage test to be used, Code Case N-416-2 requires performance of non-destructive examination in accordance with the methods and acceptance criteria of the applicable Subsection of the 1992 Edition of ASME Code,Section III, no Addenda.
ASME Section III, 1992 Edition includes the following:
Paragraph NB-5111 (ASME Class 1)
Radiographic examination shall be in accordance with Section V, Article 2, except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NB-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V]
Table NB-5111-1 only refers to use of hole-type penetrameters; use of wire-type penetrameters is not addressed.
Paragraph NC-5111 (ASME Class 2) of ASME Section III, 1992 Edition Radiographic examination shall be in accordance with Section V, Article 2, except that fluorescent screens are not permitted, the geometric unsharpness shall not exceed the limits of T-285, and the penetrameters of Table NC-5111-1 shall be used in lieu of those shown in Table T-276. [ASME Section V]
Table NC-5111-1 only refers to use of hole-type penetrameters; use of wire-type penetrameters is not addressed.
3.3 Proposed Alternative Use of wire-type IQIs as incorporated into Tables NB-5111-1 (Class 1) and NC-5111-1 (Class 2) in the 1993 Addenda of the 1992 Edition of the ASME Code,Section III.
3.4 Licensees Basis for Alternative (As Stated)
Wire-type penetrameters provide the same function as hole-type penetrameters by indicating changes in thickness and spatial resolution of the image. The one-inch minimum length of the wire eliminates the problem of indicator loss due to distortion, anomalies, and part geometry that is commonly found with the target hole in plaque type penetrameters. For more complex configurations, wire-type penetrameters are superior in that placement is directly across the area of interest, encompassing the object's range of density and geometry without using shim blocks and pipe standards.
Wire-type penetrameters have shown sensitivity equivalent to that of hole-type penetrameters as documented in Table 4 of ASME Section V, Article 22, Standard SE-747. Because of its equivalent sensitivity, a wire-type penetrameter will provide results equivalent to those of a hole-type penetrameter. Therefore, the proposed alternative will maintain the quality of the examination results.
Penetrameter requirements for performing radiography are specified by Tables NB-5111-1 (ASME Class 1) and NC-5111-1 (ASME Class 2) of ASME Section III, 1992 Edition. Based on these tables, only hole-type penetrameters can be used. Wire-type penetrameters are not included in the 1992 Edition of
[ASME Code,] Section III. [In the 1992 Edition, 1993 Addenda] of ASME Section III, Tables NB-5111-1 and NC-5111-1 were revised to include wire-type penetrameter requirements. The 1992 Edition with 1993 Addenda of ASME
[Code,] Section III, includes the provision for use of equivalent wire-type penetrameters, [and] is endorsed by the NRC in 10 CFR 50.55a. Consequently, as of the 1993 Addenda to [ASME Code,] Section III. [The NRC staff has determined that] wire-type penetrameters are acceptable for use when performing radiography.
The proposed alternative to use wire-type image quality indicators for radiography examinations as provided for in ASME [Code,] Section III, 1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. Therefore, STPNOC requests that application of the proposed alternative at the South Texas Project be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
4.0 EVALUATION STPNOCs use of a system leakage test in accordance with Code Case N-416-2; as an alternative to system hydrostatic testing as required by IWA-4700, ASME Code,Section XI; has been approved by the NRC staff. Code Case 416-2 requires the licensee to perform non-destructive examinations in accordance with the methods and acceptance criteria of the 1992 Edition of the ASME Code,Section III, no Addenda. The applicable subsections are NB-5111 and NC-5111, and Tables NB-5111-1 and NC-5111-1. Wire-type IQIs were not included in the ASME Code,Section III, until the 1992 Edition with 1993 Addenda. The 1992 Edition with 1993 Addenda of the ASME Code has been endorsed by the NRC in 10 CFR 50.55a, including the use of wire type IQIs.
Volume 17 of the Ninth Edition of the American Society of Materials (ASM) Handbook Series, published in 1989, states that wire-type penetrameters are widely used in Europe, and a standard design is used in the United Kingdom, Germany, the Netherlands, and Scandinavia.
The International Organization for Standardization and the International Institute of Welding have also adopted the wide use of wire-type penetrameters. Also, the handbook states that wire-type penetrameters specified in the American Society for Testing and Materials (ASTM) standard E 747-87 are widely used in the United States. The specifications in the handbook were developed in a public forum, and with public consensus. The ASTM Standard E 747-87 referenced in the ASM Handbook is identical to the 1989 Edition of ASMEs Standard SE-747-87.
Based on its previous endorsement of the1992 Edition with 1993 Addenda of the ASME Code, and the widespread use of wire-type penetrameters in industry, the NRC staff has determined that the wire-type penetrameters listed in Table NB-5111-1 (NC-5111-1) to the 1992 Edition with 1993 Addenda of the ASME Code will provide comparable density measurements; and, therefore, will provide an acceptable level of quality and safety.
5.0 CONCLUSION
Based on the above evaluation, the NRC staff concludes that the proposed alternative to use wire-type IQIs for radiography examinations as provided for in ASME Code,Section III, 1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety.
Pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the STPNOC to use the proposed alternative for the duration of the second 10-year ISI interval at South Texas Project, Units 1 and 2.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Isaac A. Anchondo Date: March 1, 2007
