|
|
| (14 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML15124A699 | | | number = ML15124A699 |
| | issue date = 05/08/2015 | | | issue date = 05/08/2015 |
| | title = Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities (TAC Nos. MF5866 and MF5867) | | | title = (Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities |
| | author name = Miller G E | | | author name = Miller G |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Henderson K | | | addressee name = Henderson K |
| Line 9: |
Line 9: |
| | docket = 05000413, 05000414 | | | docket = 05000413, 05000414 |
| | license number = NPF-035, NPF-052 | | | license number = NPF-035, NPF-052 |
| | contact person = Miller G E | | | contact person = Miller G |
| | case reference number = TAC MF5866, TAC MF5867 | | | case reference number = TAC MF5866, TAC MF5867 |
| | document type = Code Relief or Alternative, Letter, Safety Evaluation | | | document type = Code Relief or Alternative, Letter, Safety Evaluation |
| | page count = 6 | | | page count = 6 |
| | project = TAC:MF5866, TAC:MF5867 | | | project = TAC:MF5866, TAC:MF5867 |
| | stage = | | | stage = Other |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York,. SC 297 45 May 8, 2015 SUBJECT: CATAWBA NUCLEAR STATION, UNITS 1AND2 (CATAWBA REQUEST TO USE A LATER EDITION OF THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR INSERVICE INSPECTION ACTIVITIES (TAC NOS. MF5866 AND MF5867) Dear Mr. Henderson: By letter dated March 16, 2015 (Accession No. ML 15077A061), Duke Energy Carolinas, LLC (Duke) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv}, Duke requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code, Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b). As documented in the enclosed safety evaluation, the NRC staff has concluded that Duke has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 8, 2015 Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York,. SC 297 45 |
| K. Henderson -2 -If you have any questions, please call me at 301-415-2481. Docket Nos. 50-413 and 50-414 Enclosure: Safety Evaluation cc w/encl: Distribution via Listserv Sincer:ly/ . ,) G. Edward Miller, Project Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUEST TO USE A LATER EDITION AND ADDENDA OF ASME BOILER AND PRESSURE VESSEL, SECTION XI, CODE FOR INSERVICE INSPECTION ACTIVITIES DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 1.0 INTRODUCTION By letter dated March 16, 2015 (Accession No. ML 15077A061), Duke Energy Carolinas, LLC (the licensee) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code). The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv), the licensee requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code, Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b). 2.0 REGULATORY EVALUATION Pursuant to 10 CFR 50.55a(g)(4)(iv) "Applicable ISi Code: Use of subsequent Code editions and addenda," inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of 1 O CFR 50.55a, subject to the conditions listed in paragraph (b) of 10 CFR 50.55a, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met. Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to authorize the use of subsequent editions and addenda of the ASME Code requested by the licensee. Enclosure | | |
| -2 -3.0 TECHNICAL EVALUATION 3.1 Components Affected The components affected are ASME Code Class 1 pressure retaining welds in valve bodies. In accordance with IWB-2500 (Table IWB-2500-1) of the 1998 Edition through 2000 Addenda of the ASME Code, Section XI, these welds are classified as Examination Category B-M-1. 3.2 Applicable Code and Edition and Addenda The code of record for the third 10-year ISi interval is the 1998 Edition through 2000 Addenda of
| | ==SUBJECT:== |
| * the ASME Code. . . 3.3 Duration of Request The licensee submitted this request for the remainder of the third 10-year ISi interval at Catawba, Unit 1, which commenced on June 29, 2005, and will end on June 29, 2016, and Unit 2, which commenced on October 15, 2005, and will end on February 19, 2017. 3.4 ASME Code Requirement The 1998 Edition through 2000 Addenda of the ASME Code, Section XI, IWB-2500, Table IWB-2500-1, Examination Category B-M-1, requires Class 1 pressure retaining welds in valve bodies be subjected to surface or volumetric examination every inspection interval. 3.5 Request The licensee requested to use a portion of the 2007 Edition through 2008 Addenda of the ASME | | CATAWBA NUCLEAR STATION, UNITS 1AND2 (CATAWBA 1AND2)- |
| * Code, Section XI, that is applicable to Examination Category B-M-1 (Table IWB-2500-1). Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the 2007 Edition through 2008 Addenda of the ASME Code; 3.6 Basis for Request The licensee stated that because the 2007 Edition through 2008 Addenda of the ASME Code has no ISi requirement for Examination Category B-M-1, thereby, eliminates the radiological dose that would otherwise be incurred by performing the examinations. | | REQUEST TO USE A LATER EDITION OF THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR INSERVICE INSPECTION ACTIVITIES (TAC NOS. MF5866 AND MF5867) |
| -3 -3. 7 NRC Staff Evaluation The NRC staff has evaluated this request pursuant to 10 CFR 50.55a(g)(4)(iv). The NRC staff review focused on whether the requirements of 10 CFR 50.55a(g)(4)(iv) are met. The NRC staff confirmed that:
| | |
| | ==Dear Mr. Henderson:== |
| | |
| | By letter dated March 16, 2015 (Accession No. ML15077A061), Duke Energy Carolinas, LLC (Duke) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2. |
| | Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv}, |
| | Duke requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code, Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b). |
| | As documented in the enclosed safety evaluation, the NRC staff has concluded that Duke has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). |
| | Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017. |
| | |
| | K. Henderson If you have any questions, please call me at 301-415-2481. |
| | Sincer:ly/ . , ) |
| | VDb"/1'~'1 G. Edward Miller, Project ~anager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 |
| | |
| | ==Enclosure:== |
| | |
| | Safety Evaluation cc w/encl: Distribution via Listserv |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUEST TO USE A LATER EDITION AND ADDENDA OF ASME BOILER AND PRESSURE VESSEL, SECTION XI, CODE FOR INSERVICE INSPECTION ACTIVITIES DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By letter dated March 16, 2015 (Accession No. ML15077A061), Duke Energy Carolinas, LLC (the licensee) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code). The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2. |
| | Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv), |
| | the licensee requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code, Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b). |
| | |
| | ==2.0 REGULATORY EVALUATION== |
| | |
| | Pursuant to 10 CFR 50.55a(g)(4)(iv) "Applicable ISi Code: Use of subsequent Code editions and addenda," inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of 10 CFR 50.55a, subject to the conditions listed in paragraph (b) of 10 CFR 50.55a, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met. |
| | Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to authorize the use of subsequent editions and addenda of the ASME Code requested by the licensee. |
| | Enclosure |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | 3.1 Components Affected The components affected are ASME Code Class 1 pressure retaining welds in valve bodies. In accordance with IWB-2500 (Table IWB-2500-1) of the 1998 Edition through 2000 Addenda of the ASME Code, Section XI, these welds are classified as Examination Category B-M-1. |
| | 3.2 Applicable Code and Edition and Addenda The code of record for the third 10-year ISi interval is the 1998 Edition through 2000 Addenda of |
| | * the ASME Code. . . |
| | 3.3 Duration of Request The licensee submitted this request for the remainder of the third 10-year ISi interval at Catawba, Unit 1, which commenced on June 29, 2005, and will end on June 29, 2016, and Unit 2, which commenced on October 15, 2005, and will end on February 19, 2017. |
| | 3.4 ASME Code Requirement The 1998 Edition through 2000 Addenda of the ASME Code, Section XI, IWB-2500, Table IWB-2500-1, Examination Category B-M-1, requires Class 1 pressure retaining welds in valve bodies be subjected to surface or volumetric examination every inspection interval. |
| | 3.5 Request The licensee requested to use a portion of the 2007 Edition through 2008 Addenda of the ASME |
| | * Code, Section XI, that is applicable to Examination Category B-M-1 (Table IWB-2500-1). |
| | Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the 2007 Edition through 2008 Addenda of the ASME Code; 3.6 Basis for Request The licensee stated that because the 2007 Edition through 2008 Addenda of the ASME Code has no ISi requirement for Examination Category B-M-1, thereby, eliminates the radiological dose that would otherwise be incurred by performing the examinations. |
| | : 3. 7 NRC Staff Evaluation The NRC staff has evaluated this request pursuant to 10 CFR 50.55a(g)(4)(iv). The NRC staff review focused on whether the requirements of 10 CFR 50.55a(g)(4)(iv) are met. |
| | The NRC staff confirmed that: |
| * The licensee's proposed 2007 Edition through 2008 Addenda of the ASME Code is incorporated by reference in 10 CFR 50.55a(a); | | * The licensee's proposed 2007 Edition through 2008 Addenda of the ASME Code is incorporated by reference in 10 CFR 50.55a(a); |
| * 10 CFR 50.55a(b) has no conditions for Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies; | | * 10 CFR 50.55a(b) has no conditions for Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies; |
| * This submittal serves as the licensee's request for the NRC approval, for the use of a portion of subsequent editions and addenda of the ASME Code (i.e., 2007 Edition through 2008 Addenda for Examination Category B-M-1); | | * This submittal serves as the licensee's request for the NRC approval, for the use of a portion of subsequent editions and addenda of the ASME Code (i.e., 2007 Edition through 2008 Addenda for Examination Category B-M-1); |
| * For the portion of the 2007 Edition through 2008 Addenda that is to be used, there are no related requirements because Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the respective editions or addenda. Therefore, the NRC staff finds that the licensee satisfied all the requirements in 10 CFR 50.55a(g)(4)(iv), therefore, use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code applicable to the welds under consideration is acceptable. | | * For the portion of the 2007 Edition through 2008 Addenda that is to be used, there are no related requirements because Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the respective editions or addenda. |
| * 4.0 CONCLUSION As set forth above, the NRC staff determined that use of subsequent editions and addenda of the ASME Code, Section XI, requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 1 O CFR 50.55a(g)(4)(iv). Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017. All other ASME Code, Section XI, requirements for which relief was not specifically requested and authorized herein by the staff remain applicable, including the third party review by the Authorized Nuclear lnseniice Inspector.
| | Therefore, the NRC staff finds that the licensee satisfied all the requirements in 10 CFR 50.55a(g)(4)(iv), therefore, use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code applicable to the welds under consideration is acceptable. |
| | |
| | ==4.0 CONCLUSION== |
| | |
| | As set forth above, the NRC staff determined that use of subsequent editions and addenda of the ASME Code, Section XI, requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017. |
| | All other ASME Code, Section XI, requirements for which relief was not specifically requested and authorized herein by the staff remain applicable, including the third party review by the Authorized Nuclear lnseniice Inspector. |
| * Principal Contributors: A. Rezai Date: May 8, 2015. | | * Principal Contributors: A. Rezai Date: May 8, 2015. |
| K. Henderson -2 -If you have any questions, please call me at 301-415-2481. Docket Nos. 50-413 and 50-414 Enclosure: Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-1 R/F RidsAcrsAcnw _MailCTR Resource RidsNrrLASFigueroa Resource RidsNrrDeEpnb Resource ADAMS Accession No. ML 15124A699 Sincerely, /RA/ G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsRgn2Mai1Center Resource RidsNrrDorlOpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrPMCatawba Resource *Via SE Input OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DE/EPNB/BC DORL/LPL2-1/BC NAME GE Miller SFigueroa DAiiey* RPascarelli DATE 05/04/15 05/04/15 04/29/15 05/08/15 OFFICIAL RECORD COPY
| | |
| }} | | ML15124A699 *Via SE Input OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DE/EPNB/BC DORL/LPL2-1/BC NAME GE Miller SFigueroa DAiiey* RPascarelli DATE 05/04/15 05/04/15 04/29/15 05/08/15}} |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23151A3482023-05-30030 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023
Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22213A2532022-08-31031 August 2022
Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method
ML22007A3452022-01-11011 January 2022
Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885
ML21029A3352021-02-16016 February 2021
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019
Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)
RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018
Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2
ML18016A1782018-01-24024 January 2018
Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032)
ML17331A0862017-12-26026 December 2017
Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads
ML17104A1102017-04-26026 April 2017
Relief Request CN Grr 01, Alternative to the Testing Frequencies in the American Society of Mechanical Engineers Operation and Maintenance Code, by Adoption of Code Case OMN-20, Inservice Test Frequencies (CAC Nos. MF9595-6)
CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017
Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing
ML15301A5442015-11-10010 November 2015
Proposed Relief Request 15-CN-001, Alternative Repair of a Main Steam System Braided Flex-Hose
CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)2015-07-16016 July 2015
Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)
ML15161A3762015-06-19019 June 2015
Proposed Relief Request 14-CN-002, Alternative to American Society of Mechanical Engineers (ASME) Section XI Requirements for Class 3 Buried Piping
ML15124A6992015-05-0808 May 2015
(Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities
ML14295A5322014-10-30030 October 2014
Proposed Relief Request 14-CN-001, American Society of Mechanical Engineers (ASME) Section IX Volumetric Examination Requirements
ML14079A5462014-03-26026 March 2014
Proposed Relief Request 13-CN-003, Request for Alternative to the Requirement of IWB-2500, Table IWB-2500-1, Category B-A and Category B-D for Reactor Pressure Vessel Welds
ML11187A0012011-07-14014 July 2011
Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld
ML1012501702010-05-0303 May 2010
Withdrawal of Request for Relief Number 09-CN-001, Limited Weld Examinations During the End-of-Cycle 17 Refueling Outage
ML0912401562009-05-27027 May 2009
Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping
ML0902301722009-01-16016 January 2009
Response to NRC Requests for Additional Information and Request for Relief (Alternative) Number 08-CN-002 - Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays
ML0831506302008-11-0606 November 2008
Transmittal of Request for Relief Number 08-CN-002, Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays (Fswols)
ML0822403862008-09-12012 September 2008
Relief 06-CN-003, Use of Polyethylene Material in Nuclear Safety-Related Piping Applications
ML0815607342008-07-0707 July 2008
Request for Relief 07-CN-001, Limited Weld Examinations During End-Of -Cycle 14 Refueling Outage
ML0816000032008-07-0101 July 2008
Request for Relief 07-CN-002, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage
ML0731804472007-08-27027 August 2007
Request for Relief Number 07-CN-004 Limited Weld Examinations During the End-of-Cycle 16 Refueling Outage
ML0706504172007-02-26026 February 2007
Submittal of Request for Relief Number 07-CN-003, Request for Relief to Allow Use of Alternate Requirements for Snubber Inspection & Testing
ML0636000142007-01-0909 January 2007
Relief, Request to Use a Portion of a Letter Edition of ASME Code
ML0632801882006-11-16016 November 2006
Revision to Relief Request 06-GO-001
ML0623900202006-09-25025 September 2006
Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage, MC8337, MC9171, MC9172, MC9173, MC9174, MC9175, MC9176, MC9177, MC9178, and MC9179)
ML0626202612006-09-11011 September 2006
Relief Request 06-GO-001 Request for Additional Information
ML0622304212006-09-0707 September 2006
Relief, Request for Relief for Snubber Visual Examination and Functional Testing Related to the Third 10-year Interval Inservice Inspection Program
ML0634903992006-07-27027 July 2006
Relief Request 06-GO-001
ML0616603262006-07-20020 July 2006
Request for Use of Later Edition and Addenda of the ASME Code
ML0616800102006-07-19019 July 2006
Regarding Request for Relief 05-CN-001, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage
ML0535503702006-04-0303 April 2006
Relief, O5-CN-003 Limited Weld Examination Coverage
ML0517801882005-07-25025 July 2005
RR 04-CN-001, Volumetric Weld Inspection Requirements
ML0519403672005-07-13013 July 2005
Relief Request MC3057, 04-CN-002, Limited Weld Examinations During End-of-Cycle 12 Refueling Outage
ML0518901432005-06-28028 June 2005
Submittal of Third Ten-Year Interval Inservice Inspection Plan for Steam Generator Tubing
ML0517801642005-06-23023 June 2005
RR 04-CN-004, Class 1 ISI Pressure Test Boundaries Requirement (Tac No. MC3276, MC3277)
ML0510203642005-03-31031 March 2005
Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at Catawba Nuclear Station, Unit 2 in Accordance with 10 CFR 50.55a(g) (4) (IV)
ML0504105322005-03-17017 March 2005
RR, Alternative Code of Prv Nozzle Welds for Volumetic Examination RR-04-GO-001
ML0504904622005-02-17017 February 2005
Relief, RR No. 03-001, 10 CFR Section 50.55a (a)(3)(ii) for Second ISI Intervals
ML0428106012004-10-20020 October 2004
Relief Request, Alternate to the American Society of Mechanical Engineers Section XI for Reactor Vessel Examinations RR-04-GO-001
ML0427400272004-09-30030 September 2004
Relief, Amended Relief Request 03-GO-010 Requesting Use of Subsequent Edition and Addenda of the ASME Code for Class Mc and CC Components (MC9674-MC9680)
ML0427302912004-09-29029 September 2004
Request for Relief, 04-GO-006, for Use of an Alternate Code Case to Use Ultrasonic Techniques Equipment
ML0420403942004-07-20020 July 2004
Request for Relief 03-004, Minimum Percentage Requirements for Second Period of the Second Inservice Inspection Interval
2023-09-25
[Table view]
Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024
Integrated Inspection Report 05000413-2023004 and 05000414-2023004
ML24005A2512024-01-26026 January 2024
Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
ML23317A3462023-11-14014 November 2023
Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
IR 05000413/20230102023-10-11011 October 2023
NRC Inspection Report 05000413/2023010 and 05000414/2023010
ML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
IR 05000413/20230052023-08-25025 August 2023
Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005)
ML23233A1692023-08-17017 August 2023
EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l
IR 05000413/20230022023-07-25025 July 2023
Integrated Inspection Report 05000413/2023002 and 05000414/2023002
ML23207A0762023-07-14014 July 2023
EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06
ML23237A2672023-06-13013 June 2023
June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414
ML23159A0052023-06-0505 June 2023
56557-EN 56557 - Paragon - Redlined
IR 05000413/20230012023-05-0505 May 2023
Integrated Inspection Report 05000413/2023001 and 05000414/2023001
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
IR 05000413/20230112023-04-25025 April 2023
Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011
ML23107A2542023-04-14014 April 2023
301 Examination Report Letter and Report (Merged)
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
IR 05000413/20220062023-03-0101 March 2023
Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006)
IR 05000413/20234012023-03-0101 March 2023
Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401
IR 05000413/20233012023-02-17017 February 2023
Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301
IR 05000413/20220042023-01-31031 January 2023
Integrated Inspection Report 05000413/2022004 and 05000414/2022004
IR 05000413/20220112022-12-15015 December 2022
Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011
ML22356A0512022-12-14014 December 2022
Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
IR 05000413/20224032022-11-17017 November 2022
Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public)
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
ML22319A0942022-11-10010 November 2022
EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105
IR 05000414/20220032022-10-31031 October 2022
Integrated Inspection Report 05000414/2022003 and 05000414/2022003
IR 05000413/20224022022-10-28028 October 2022
Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402
ML22297A2642022-10-25025 October 2022
Project Manager Assignment
ML22276A2492022-10-25025 October 2022
Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue
ML22303A0052022-10-24024 October 2022
EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC
ML22258A0302022-09-15015 September 2022
Evacuation Time Estimate Reports
ML22242A0022022-09-12012 September 2022
Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition
ML22231B1362022-09-0101 September 2022
Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi
ML22303A0042022-08-31031 August 2022
Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali
IR 05000413/20220052022-08-26026 August 2022
Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005
ML22217A0792022-08-0303 August 2022
301, Corporate Notification Letter (210-day Ltr)
IR 05000413/20220022022-07-29029 July 2022
Integrated Inspection Report 05000413/2022002 and 05000414/2022002
IR 07200045/20220012022-07-26026 July 2022
Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001
ML22215A2502022-07-25025 July 2022
EN 55960 - Update - Curtiss Wright
IR 05000413/20220102022-07-21021 July 2022
Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010
ML22195A2432022-07-19019 July 2022
Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative
ML22164A0362022-07-19019 July 2022
Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public
ML22199A2552022-07-0606 July 2022
Ds Catawba 2022 RQ Inspection Notification Letter
ML22222A0092022-07-0101 July 2022
EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator
ML22175A0342022-06-28028 June 2022
Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403
ML22046A0222022-06-14014 June 2022
Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML22111A3572022-05-16016 May 2022
Letter Issuing Exemption to Catawba
IR 05000414/20220012022-04-28028 April 2022
Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001
2024-02-02
[Table view]
Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
ML22242A0022022-09-12012 September 2022
Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition
ML22213A2532022-08-31031 August 2022
Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method
ML22164A0362022-07-19019 July 2022
Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public
ML22046A0222022-06-14014 June 2022
Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML22010A2812022-03-0404 March 2022
Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161
ML22007A3452022-01-11011 January 2022
Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885
ML21266A0112021-10-0505 October 2021
Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A
ML21253A0822021-09-20020 September 2021
Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method
ML21155A2132021-08-26026 August 2021
Plant
ML21131A0262021-06-23023 June 2021
Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage
ML21113A0132021-05-0606 May 2021
Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities
ML21029A3352021-02-16016 February 2021
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20300A2062020-11-0909 November 2020
Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20258A2712020-09-21021 September 2020
Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268
ML20083F9272020-08-12012 August 2020
Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description
ML20174A0452020-08-0404 August 2020
Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits
ML19296D1192020-01-31031 January 2020
Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability
ML19254A6202019-09-17017 September 2019
Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography
ML19212A6552019-08-27027 August 2019
Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating
ML19191A0612019-07-15015 July 2019
Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2018 Refueling Outage 24
ML19058A6322019-07-0101 July 2019
Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs
ML19128A3262019-06-20020 June 2019
Alternative to Depth Sizing Qualification Examination of Welds
ML19121A5512019-06-17017 June 2019
Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves
ML19050A2972019-04-18018 April 2019
McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal
ML18275A2782018-11-28028 November 2018
Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration
ML18172A1722018-08-15015 August 2018
Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
ML18016A1782018-01-24024 January 2018
Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032)
ML17296A2082018-01-0404 January 2018
Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026)
ML17331A0862017-12-26026 December 2017
Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads
ML17261B2902017-10-23023 October 2017
Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024
ML17257A2972017-10-23023 October 2017
Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043)
ML17254A1442017-10-23023 October 2017
Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031)
ML17249A1352017-09-29029 September 2017
Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0
ML17188A3872017-08-21021 August 2017
Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660)
ML17172A4282017-07-26026 July 2017
Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0
ML17165A4412017-07-21021 July 2017
Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017
ML17055A6472017-05-0808 May 2017
Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429)
ML17066A3742017-04-26026 April 2017
Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML16137A3082017-02-0808 February 2017
Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805
ML16277A4042016-10-20020 October 2016
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16208A2832016-08-0808 August 2016
Correction to Issuance of Amendments Regarding Use of Optimized Zirlo
ML16159A3362016-07-19019 July 2016
Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486)
ML16105A3262016-06-21021 June 2016
Issuance of Amendments Regarding Use of Optimized Zirlo
ML16124A6942016-06-0202 June 2016
Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
2023-09-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 8, 2015 Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York,. SC 297 45
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2 (CATAWBA 1AND2)-
REQUEST TO USE A LATER EDITION OF THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR INSERVICE INSPECTION ACTIVITIES (TAC NOS. MF5866 AND MF5867)
Dear Mr. Henderson:
By letter dated March 16, 2015 (Accession No. ML15077A061), Duke Energy Carolinas, LLC (Duke) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv},
Duke requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b).
As documented in the enclosed safety evaluation, the NRC staff has concluded that Duke has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv).
Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017.
K. Henderson If you have any questions, please call me at 301-415-2481.
Sincer:ly/ . , )
VDb"/1'~'1 G. Edward Miller, Project ~anager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUEST TO USE A LATER EDITION AND ADDENDA OF ASME BOILER AND PRESSURE VESSEL, SECTION XI, CODE FOR INSERVICE INSPECTION ACTIVITIES DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated March 16, 2015 (Accession No. ML15077A061), Duke Energy Carolinas, LLC (the licensee) requested to use a portion of the requirements of subsequent editions and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code). The request pertains to inservice inspection (ISi) of Class 1 pressure retaining welds in valve bodies at the Catawba Nuclear Station, Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),
the licensee requested to use a portion of requirements of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for ISi of the Class 1 pressure retaining welds in valve bodies, subject to conditions listed in 10 CFR 50.55a(b).
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g)(4)(iv) "Applicable ISi Code: Use of subsequent Code editions and addenda," inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of 10 CFR 50.55a, subject to the conditions listed in paragraph (b) of 10 CFR 50.55a, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to authorize the use of subsequent editions and addenda of the ASME Code requested by the licensee.
Enclosure
3.0 TECHNICAL EVALUATION
3.1 Components Affected The components affected are ASME Code Class 1 pressure retaining welds in valve bodies. In accordance with IWB-2500 (Table IWB-2500-1) of the 1998 Edition through 2000 Addenda of the ASME Code,Section XI, these welds are classified as Examination Category B-M-1.
3.2 Applicable Code and Edition and Addenda The code of record for the third 10-year ISi interval is the 1998 Edition through 2000 Addenda of
3.3 Duration of Request The licensee submitted this request for the remainder of the third 10-year ISi interval at Catawba, Unit 1, which commenced on June 29, 2005, and will end on June 29, 2016, and Unit 2, which commenced on October 15, 2005, and will end on February 19, 2017.
3.4 ASME Code Requirement The 1998 Edition through 2000 Addenda of the ASME Code,Section XI, IWB-2500, Table IWB-2500-1, Examination Category B-M-1, requires Class 1 pressure retaining welds in valve bodies be subjected to surface or volumetric examination every inspection interval.
3.5 Request The licensee requested to use a portion of the 2007 Edition through 2008 Addenda of the ASME
Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the 2007 Edition through 2008 Addenda of the ASME Code; 3.6 Basis for Request The licensee stated that because the 2007 Edition through 2008 Addenda of the ASME Code has no ISi requirement for Examination Category B-M-1, thereby, eliminates the radiological dose that would otherwise be incurred by performing the examinations.
- 3. 7 NRC Staff Evaluation The NRC staff has evaluated this request pursuant to 10 CFR 50.55a(g)(4)(iv). The NRC staff review focused on whether the requirements of 10 CFR 50.55a(g)(4)(iv) are met.
The NRC staff confirmed that:
- 10 CFR 50.55a(b) has no conditions for Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies;
- This submittal serves as the licensee's request for the NRC approval, for the use of a portion of subsequent editions and addenda of the ASME Code (i.e., 2007 Edition through 2008 Addenda for Examination Category B-M-1);
- For the portion of the 2007 Edition through 2008 Addenda that is to be used, there are no related requirements because Examination Category B-M-1 or Class 1 pressure retaining welds in valve bodies were removed from the respective editions or addenda.
Therefore, the NRC staff finds that the licensee satisfied all the requirements in 10 CFR 50.55a(g)(4)(iv), therefore, use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code applicable to the welds under consideration is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determined that use of subsequent editions and addenda of the ASME Code,Section XI, requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff authorizes use of a portion of the 2007 Edition through 2008 Addenda of the ASME Code for the welds under consideration for the reminder of the third 10-year ISi interval in Catawba, Unit 1, which will end on June 29, 2016, and Unit 2, which will end on February 19, 2017.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the staff remain applicable, including the third party review by the Authorized Nuclear lnseniice Inspector.
- Principal Contributors: A. Rezai Date: May 8, 2015.
ML15124A699 *Via SE Input OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DE/EPNB/BC DORL/LPL2-1/BC NAME GE Miller SFigueroa DAiiey* RPascarelli DATE 05/04/15 05/04/15 04/29/15 05/08/15
