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MONTHYEARML0134802382002-01-18018 January 2002 Safety Evaluation of Request to Use Alternative Materials Per Associated Code Cases for Steam Generator Channel Head Bowl Drain Nozzle and Weld Repairs Project stage: Approval 2002-01-18
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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:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) 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 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 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) 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) 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) 2024-07-12
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January 18, 2002 Mr. G. R. Peterson Site Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745-9635
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 2 RE: SAFETY EVALUATION OF REQUEST TO USE ALTERNATIVE MATERIALS PER ASSOCIATED CODE CASES FOR STEAM GENERATOR CHANNEL HEAD BOWL DRAIN NOZZLE AND WELD REPAIRS (TAC NO. MB3003)
Dear Mr. Peterson:
By letter dated September 26, 2001, Duke Energy Corporation requested approval of the proposed alternative to use Alloy 690 welding filler materials (Inconel or Alloy 52/152) and associated American Society of Mechanical Engineers Code Cases 2142-1 and 2143-1 at Catawba Nuclear Station, Unit 2. The request is associated with the use of Alloy 690 type filler material (Inconel 52/152) for the steam generator channel head bowl drain nozzle and weld repairs.
The staff concludes that the use of the proposed alternative for this repair will provide an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i), the staff authorizes the use of the proposed alternative. Our evaluation addresses the use of Alloy 690 material and not the repair methodology outlined in the submittal. Our Safety Evaluation is enclosed.
Sincerely,
/RA/
Richard Laufer, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-414
Enclosure:
As stated cc w/encl: See next page Mr. G. R. Peterson January 18, 2002 Site Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745-9635
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 2 RE: SAFETY EVALUATION OF REQUEST TO USE ALTERNATIVE MATERIALS PER ASSOCIATED CODE CASES FOR STEAM GENERATOR CHANNEL HEAD BOWL DRAIN NOZZLE
AND WELD REPAIRS (TAC NO. MB3003)
Dear Mr. Peterson:
By letter dated September 26, 2001, Duke Energy Corporation requested approval of the proposed alternative to use Alloy 690 welding filler materials (Inconel or Alloy 52/152) and associated American Society of Mechanical Engineers Code Cases 2142-1 and 2143-1 at Catawba Nuclear Station, Unit 2. The request is associated with the use of Alloy 690 type filler material (Inconel 52/152) for the steam generator channel head bowl drain nozzle and weld repairs.
The staff concludes that the use of the proposed alternative for this repair will provide an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i), the staff authorizes the use of the proposed alternative. Our evaluation addresses the use of Alloy 690 material and not the repair methodology outlined in the submittal. Our Safety Evaluation is enclosed.
Sincerely,
/RA/
Richard Laufer, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-414
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC CPatel ACRS PDII-1 R/F CHawes RII RLaufer OGC Accession Number: ML013480238 *See previous concurrence OFC PM/PDII-1 LA/PD PDII-1 EMCB* OGC* ASC/PDII-1 NAME CPatel CPatel for CHawes BElliot RHoefling RLaufer DATE 01/18/02 01/18/02 01/08/02 01/15/02 01/18/02 OFFICIAL RECORD COPY SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE ALTERNATIVE MATERIALS AND ASSOCIATED CODE CASES FOR REPAIRS ASSOCIATED WITH STEAM GENERATOR CHANNEL HEAD
BOWL DRAIN NOZZLE AND WELDS DUKE ENERGY CORPORATION CATAWBA NUCLEAR STATION, UNIT 2 DOCKET NO. 50-414
1.0 INTRODUCTION
By letter dated September 26, 2001, Duke Energy Corporation (the licensee) requested approval under the provisions of Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.55a(a)(3)(i) to use Alloy 690 weld filler materials (Inconel or Alloy 52/152) in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Case 2142-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS N06052 Filler Metal,Section XI, and Code Case 2143-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS W86152 Welding Electrode,Section XI. The Alloy 690 material would be used for the repair of nozzles and welds for channel head bowl drain on Westinghouse D5 steam generators at Catawba Unit 2. The referenced Code cases introduce and classify new nickel base weld metals that are compatible with Alloy 690 base metal materials. Code Case 2142-1 establishes welding classifications and other requirements for a bare wire filler metal.
Code Case 2143-1 establishes welding classifications and other requirements for a coated electrode. These two Code cases have not been incorporated by reference into the regulations; therefore, their use requires NRC approval.
Thus, the licensees request consists of two issues:
- a. The use of Alloy 690 (Inconel 52/152) weld filler materials in steam generator channel head bowl drain nozzle and weld repair in lieu of Alloy 600 (Inconel 82/182) weld filler materials; and
- b. The use of two ASME Code cases that group the new weld filler materials in the same weld categories as other commonly employed nickel base weld filler metals. This allows the use of appropriate existing welding procedures and performance qualifications with the new weld metals.
The Code of Record to be used to repair the steam generator channel head bowl drain nozzle and welds is the 1989 ASME B&PV Code Section XI with no addenda. This code allows, by reference, the use of Alloy 600 (Inconel 82/182) weld filler material, but does not include the use of Alloy 690 (Inconel 52/152) weld filler materials. Industry studies indicate that Alloy 690
(Inconel 52/152) weld filler materials are less susceptible to intergranular stress corrosion cracking (IGSCC) than the Inconel 82/182 materials. Alloy 600 type weld metals (Inconel 82/182) were widely used during the construction of nuclear power plants. Operating experience has shown that Inconel 182 weld material is susceptible to IGSCC, although primarily in boiling-water reactor (BWR) environments.
2.0 DISCUSSION 2.1 Alloy 690 weld filler materials (Inconel 52/152)
The licensee stated that the industry studies have demonstrated that Alloy 690 weld materials possess a high resistance to primary water corrosion. In addition, an evaluation by the licensee of the possible weld dilution concluded that the percentage of chromium in the deposited welds will exceed 22 percent. Consequently, the chromium content of the repaired surfaces containing the proposed Alloy 690 weld material, considering chromium dilution, will exceed that of the original Alloy 600 material, and thus is expected to have good corrosion resistance.
The licensee has proposed the use of alternative Inconel 52/152 materials for weld repairs associated with the steam generator channel head bowl drain nozzle and welds. Laboratory test data have shown that Inconel 52/152 materials are resistant to stress corrosion cracking in simulated pressurized-water reactor (PWR) and BWR environments. The material properties of the existing Alloy 600 (82/182) weld material were compared by the licensee to the new proposed Alloy 690 (52/152) weld material. The thermal expansion coefficient of the 52/152 weld material is somewhat higher than the coefficient of the 82/182 weld material; however, the modulus of elasticity is lower for the 52/152 weld material than the 82/182 weld material. Since the thermal stress is a function of the product of the modulus of elasticity and the thermal expansion coefficient, the effects tend to cancel each other. Thus, the presence of the two weld materials will have an insignificant effect on the thermal stresses in the total weld.
The staff has approved the use of Inconel 52/152 in the replacement of steam generators for a number of PWRs, including V. C. Summer; St. Lucie, Unit 1; McGuire Nuclear Station, Units 1 and 2; Catawba Nuclear Station, Unit 1; and Oconee Nuclear Station, Units 1, 2, and 3. The staff also has approved use of Inconel 52/152 for repair of the cracks found on the Oconee Nuclear Station Units 1 and 3 Control Rod Drive Mechanisms. Therefore, the licensee-proposed use of Inconel 52/152 filler materials for repairs associated with the steam generator channel head bowl drain nozzle and welds is acceptable since it will provide an acceptable level of quality and safety.
2.2 Code Cases 2142-1 and 2143-1 The purposes of a weld metal code case are the establishment of uniform chemical and material properties and the classification of the weld metal with respect to its welding characteristics. This welding characteristics classification is known as an F-No. Weld metals with like characteristics are grouped together for welding and welder qualification purposes in order to eliminate unnecessary duplication.
Code Case 2142-1 lists American Welding Society (AWS) specification (AWS A5.14) and Unified Numbering System (UNS) designation (UNS N06052) conforming to Inco 52 (Inconel 52). It establishes the F-No. of this weld metal as F-No. 43 for both procedure and
performance qualification purposes. Code Case 2143-1 lists appropriate AWS and UNS specifications for a coated electrode matching Inco 152 (Inconel 152) and establishes F-No. 43 for this material for welding purposes. By this set of specifications and F-No. assignments, these materials are completely described for welding purposes as similar in their welding characteristics to many other Code nickel-based weld metals. Thus, these two weld metals (Inconel 52/152) are exempted from the requirements for specific procedure and performance qualifications for non-Code materials.
The staff finds that these two code cases appropriately specify and classify the necessary weld metal parameters and are acceptable for use. The staff has approved the use of these two Code cases in the replacement of steam generators for a number of PWRs, including V. C. Summer; St. Lucie, Unit 1; McGuire Nuclear Station, Units 1 and 2; Catawba Nuclear Station Unit 1; and Oconee Nuclear Station, Units 1, 2, and 3; as well as reactor vessel head penetration repairs for the Oconee Nuclear Station, Unit 1.
3.0 CONCLUSION
The use of Alloy 690 weld filler material (Inconel 52/152) and the associated ASME Code Cases 2142-1 and 2143-1 for the repairs associated with the steam generator channel head bowl drain nozzle and welds will provide superior corrosion protection over that provided by Alloy 600 (Inconel 82/182) material. The use of Alloy 690 has been previously authorized for new construction and other repair activities.
Based on the above evaluation, the staff concludes that the proposed alternative to use Alloy 690 weld filler materials (Inconel 52/152) per Code Cases 2142-1 and 2143-1 for the repairs associated with the steam generator channel head bowl drain nozzle and welds will provide an acceptable level of quality and safety. Pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the use of the proposed alternative. The use of this proposed alternative is also authorized for future repairs of the channel head bowl drain(s) for all steam generators at Catawba Nuclear Station, Unit 2.
Principal Contributor: Chandu P. Patel Date: January 18, 2002
Catawba Nuclear Station cc:
Mr. Gary Gilbert North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Energy Corporation P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident Inspector Ms. Lisa F. Vaughn U.S. Nuclear Regulatory Commission Legal Department (PB05E) 4830 Concord Road Duke Energy Corporation York, South Carolina 29745 422 South Church Street Charlotte, North Carolina 28201-1006 Virgil R. Autry, Director Division of Radioactive Waste Management Anne Cottingham, Esquire Bureau of Land and Waste Management Winston and Strawn Department of Health and Environmental 1400 L Street, NW Control Washington, DC 20005 2600 Bull Street Columbia, South Carolina 29201-1708 North Carolina Municipal Power Agency Number 1 Mr. C. Jeffrey Thomas 1427 Meadowwood Boulevard Manager - Nuclear Regulatory P. O. Box 29513 Licensing Raleigh, North Carolina 27626 Duke Energy Corporation 526 South Church Street County Manager of York County Charlotte, North Carolina 28201-1006 York County Courthouse York, South Carolina 29745 Saluda River Electric P. O. Box 929 Piedmont Municipal Power Agency Laurens, South Carolina 29360 121 Village Drive Greer, South Carolina 29651 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Ms. Karen E. Long Westinghouse Electric Company Assistant Attorney General 6000 Fairview Road North Carolina Department of Justice 12th Floor P. O. Box 629 Charlotte, North Carolina 28210 Raleigh, North Carolina 27602 Elaine Wathen, Lead REP Planner Division of Emergency Management 116 West Jones Street Raleigh, North Carolina 27603-1335
Catawba Nuclear Station cc:
Mr. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Richard M. Fry, Director Division of Radiation Protection North Carolina Department of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721