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Category:Letter type:RC
MONTHYEARRC-22-0004, (Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System2022-01-14014 January 2022 (Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System RC-18-0157, (Vcsns), Units 1, 2 and 3 Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-12-28028 December 2018 (Vcsns), Units 1, 2 and 3 Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0149, ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-12-21021 December 2018 ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0136, (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)2018-12-12012 December 2018 (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683) RC-18-0144, (Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 252018-11-20020 November 2018 (Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 25 RC-18-0126, (Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-01692018-11-0909 November 2018 (Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-0169 RC-18-0070, (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...2018-10-0808 October 2018 (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ... RC-18-0067, (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.22018-10-0808 October 2018 (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 RC-18-0123, NRC Request for Information Baseline Radiation Safety Inspection2018-10-0404 October 2018 NRC Request for Information Baseline Radiation Safety Inspection RC-18-0117, (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment2018-09-28028 September 2018 (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment RC-18-0112, (Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.32018-09-27027 September 2018 (Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.3 RC-18-0119, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-09-19019 September 2018 (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange2018-09-14014 September 2018 (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange RC-18-0116, (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information2018-09-11011 September 2018 (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information RC-18-0113, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-31031 August 2018 (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions2018-08-29029 August 2018 License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions RC-18-0111, License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-24024 August 2018 License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0100, (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information2018-08-22022 August 2018 (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..2018-08-14014 August 2018 (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water .. RC-18-0102, Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error2018-08-10010 August 2018 Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error RC-18-0098, (Vcsns), Units 1, 2 and 3 - Modification of Requested Latest Completion Date in Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-07-30030 July 2018 (Vcsns), Units 1, 2 and 3 - Modification of Requested Latest Completion Date in Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0085, (Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-01262018-07-23023 July 2018 (Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-0126 RC-18-0090, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...2018-07-12012 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request... RC-18-0089, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-11011 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping RC-18-0084, Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Requ2018-07-0303 July 2018 Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Reques RC-18-0082, Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-0303 July 2018 Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping RC-18-0079, Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error2018-06-29029 June 2018 Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error RC-18-0074, Change of the Commitment Date of DRIB/105A&B Door Submittal2018-06-18018 June 2018 Change of the Commitment Date of DRIB/105A&B Door Submittal RC-18-0060, (VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error2018-05-30030 May 2018 (VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error RC-18-0064, (Vcsns), Unit 1 - Annual Commitment Change Summary Report2018-05-18018 May 2018 (Vcsns), Unit 1 - Annual Commitment Change Summary Report RC-18-0063, Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation2018-05-0202 May 2018 Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018 (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors RC-18-0059, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report RC-18-0046, License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information2018-04-19019 April 2018 License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information2018-04-0202 April 2018 (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information RC-18-0041, Report of Status of Decommissioning Funding2018-03-28028 March 2018 Report of Status of Decommissioning Funding RC-17-0175, Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error2018-01-31031 January 2018 Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error RC-18-0006, Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-01-25025 January 2018 Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-17-0169, Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-00192017-12-11011 December 2017 Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-0019 RC-17-0182, (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status2017-12-11011 December 2017 (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status RC-17-0172, Notification of Personnel Changes2017-11-30030 November 2017 Notification of Personnel Changes RC-17-0161, Submittal of Change of the Commitment Date of DRIB/105A&B Door2017-11-28028 November 2017 Submittal of Change of the Commitment Date of DRIB/105A&B Door RC-17-0135, Annual Commitment Change Summary Report2017-11-0303 November 2017 Annual Commitment Change Summary Report RC-17-0123, Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds2017-10-30030 October 2017 Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds RC-17-0140, Transmittal of 10 CFR 50.59 Biennial Report2017-10-23023 October 2017 Transmittal of 10 CFR 50.59 Biennial Report RC-17-0107, (Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change2017-10-0606 October 2017 (Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 12017-09-27027 September 2017 Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1 RC-17-0126, Reply to a Notice of Violation, Per Inspection Report 05000395/20170022017-09-0606 September 2017 Reply to a Notice of Violation, Per Inspection Report 05000395/2017002 RC-17-0112, Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days2017-09-0101 September 2017 Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days RC-17-0069, (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description2017-08-30030 August 2017 (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description 2022-01-14
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Text
Thomas D. Gatlin Vice President, Nuclear Operations 803.345.4342 A SCANA COMPANY July 27, 2012 RC-12-0110 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12.REQUEST FOR WELD RECATEGORIZATION AND USE OF ALTERNATIVES TO ASME CODE INSPECTION INTERVAL FOR VCSNS THIRD TEN YEAR INSERVICE INSPECTION (RR-III-08)
Reference:
Letter from T. D. Gatlin, SCE&G, REQUEST FOR WELD RECATEGORIZATION FOR VCSNS STEAM GENERATOR NOZZLE TO SAFE END WELDS [PRELIMINARY SUBMITTAL
-RR-III-08], dated June 21, 2012, ADAMS Accession No. ML12177A381 Pursuant to 1 OCFR50.55a(g)(6)(ii)(F)(2) and 1 OCFR50.55a(a)(3)(ii), South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service Authority (Santee Cooper), hereby submits the attached request for recategorization for the Steam Generator Nozzle dissimilar metal welds and relief from the inspection interval.Due to the June 21, 2011 change to 1OCFR50.55a
[FR36232 Volume 76, Number 119], the primary steam generator (SG) nozzle to safe end welds are required to have a baseline inspection performed in the first outage following January 20, 2012. For VCSNS the applicable outage is RF-20 scheduled for fall 2012. The revised rule requires the use of ASME Boiler & Pressure Vessel Code (BPVC) Code Case N-770-1 with conditions specified in 10CFR50.55a(g)(6)(ii)(F).
The proposed weld categorization change will reflect the actual weld profile rather than the default A-2 and B assignment under the new rule. VCSNS initiated its request for alternative categorization to inspection Item G of Code Case N-770-1 within the referenced letter.Enclosure 1 provides the results of the flaw evaluation for the proposed weld recategorization by addressing items 11 and 12 of question 29 provided within NRC document "Summary of Public Meeting Between the Nuclear Regulatory Commission Staff and Industry Representatives on Implementation of ASME Code Case N-770-1,"[ML112240818]
dated August 12, 2011. It is anticipated that the information required to support item 5.will be submitted to the NRC in August 2012.Virgil C. Summer Station
- Post Office Box 88 .Jenkinsville, SC. 29065 .F (803) 345-5209 K I%%J Document Control Desk CR-12-00556 RC-12-0110 Page 2 of 2 VCSNS is also requesting an alternative to the implementation date requirements of 1OCFR50.55a(g)(6)(ii)(F)(3) by declaring hardship under 10CFR50.55a(a)(3)(ii).
The bases for this declaration are provided in Enclosure
- 2. The one time deferral proposed herein extends the inservice inspection interval beyond the current third interval end date of December 31, 2013.SCE&G is requesting NRC approval of the proposed alternatives by November 6, 2012 (prior to the weld being placed in service with the plant in an operating mode other than Mode 5 or 6) in accordance with 10CFR50.55a(g)(6)(ii)(F)(3).
This letter contains no commitments.
Should you have any questions, please call Bruce L. Thompson at 803-931-5042.
Very truly yours, Thomas D. Gatlin JG/TDG/gr Enclosure 1: Request For Weld Recategorization Attachment 1: Westinghouse LTR-PAFM-12-86-NP Enclosure 2: Relief Request RR-111-08 Attachment 1: Steam Generator Weld Profiles c: K. B. Marsh S. A. Byrne J. B. Archie N. S. Carns J. H, Hamilton R. J, White W. M. Cherry V. M. McCree R. E. Martin NRC Resident Inspector K. M. Sutton NSRC RTS (CR-12-00556)
File (810.19-2)
PRSF (RC-12-0110)
Document Control Desk Enclosure 1 CR-12-00556 RC-12-0110 Page 1 of 5 South Carolina Electric & Gas Co. (SCE&G)Virgil C. Summer Nuclear Station Unit 1 (VCSNS)Request For Weld Recategorization
- 1. ASME Code Component(s)
Affected The affected components are the VCSNS, Steam Generator Nozzle (Hot and Cold Leg)to Safe End Welds which are Alloy 82/182 with an Alloy 152 inlay that was originally installed during fabrication.
The VCSNS third 10-year inservice inspection (ISI) interval ends December 31, 2013.Table 1 Examination Inspection Cateqory Item Description N-770-1 A-2 Weld CGE-1-4100A-31DM, Steam Generator "A" Hot Leg Nozzle N-770-1 B Weld CGE-1-4100A-32DM, Steam Generator "A" Cold Leg Nozzle N-770-1 A-2 Weld CGE-1-4200A-28DM, Steam Generator "B" Hot Leg Nozzle N-770-1 B Weld CGE-1-4200A-29DM, Steam Generator "B" Cold Leg Nozzle N-770-1 A-2 Weld CGE-1-4300A-29DM, Steam Generator "C" Hot Leg Nozzle N-770-1 B Weld CGE-1-4300A-30DM, Steam Generator "C" Cold Leg Nozzle 2. Applicable Code Edition and Addenda ASME Code Section Xl, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda.3. Applicable Code Requirement Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation ActivitiesSection XI, Division 1." ASME Code Section XI, Division 1, "Rules for Inspection and Testing of Components of Light Water Cooled Plants." Article IWB-2500, "Examination and Pressure Test Requirements" Table IWB-2500-1, "Examination Categories" Document Control Desk Enclosure 1 CR-12-00556 RC-12-0110 Page 2 of 5 4. Reason for Request Recategorization is being requested due to the imposed rulemaking change to 1 0CFR50.55a
[FR36232 Volume 76, Number 119], issued June 21, 2011. The rulemaking change requires the use of ASME Boiler & Pressure Vessel Code (BPVC)-Code Case N-770-1 with conditions specified in 1OCFR50.55a(g)(6)(ii)(F) specifically for Class 1 Piping and Nozzle Dissimilar-Metal Butt Welds. As stated within 1 OCFR50.55a(g)(6)(ii)(F)(2):
"...all other butt welds that rely on Alloy 82/182 for structural integrity shall be categorized as Inspection Items A-I, A-2 or B until the NRC staff has reviewed the mitigation and authorized an alternative code case Inspection Item for the mitigated weld..." 5. Proposed Alternative and Basis for Use VCSNS is requesting an alternative categorization to inspection items specific to the six replacement Steam Generator Nozzle (Hot and Cold Leg) to Safe End Welds which are Alloy 82/182 with an Alloy 152 inlay that was originally applied during fabrication.
The replacement steam generators were manufactured in 1993 and installed during VCSNS outage RF8 in the fall of 1994. Based on the manufacturing process of the replacement steam generators and guidance from Code Case N-770-1, the VCSNS Steam Generator Nozzles' (Hot and Cold Leg) Safe End Welds should be categorized as Inspection Item G, "Uncracked Butt Weld Mitigated With An Inlay." South Carolina Electric & Gas Company (SCE&G) is providing the remainder of the response to items 11 and 12 that were discussed within Question 29 from "Summary Of Public Meeting Between The Nuclear Regulatory Commission Staff And Industry Representatives On Implementation Of ASME Code Case N-770-1," [ML112240818]
dated August 12, 2011. It is anticipated that the information required to support item 5 will be located and submitted to the NRC in August 2012. The other nine items and VCSNS response were provided within a letter from T. D. Gatlin, SCE&G, REQUEST FOR WELD RECATEGORIZATION FOR VCSNS STEAM GENERATOR NOZZLE TO SAFE END WELDS [PRELIMINARY SUBMITTAL
-RR-III-08], dated June 21, 2012, ADAMS Accession No. ML12177A381.
Document Control Desk Enclosure 1 CR-12-00556 RC-12-0110 Page 3 of 5 Item Description 5 qualifications of the weld procedure specifications, welders and welding operators[VCSNS Response]The replacement steam generators were fabricated at the Westinghouse Pensacola plant, using qualified nuclear component welders with many years of experience.
The weld procedures and qualifications were performed in accordance with the requirements of ASME Code Section III NCA-4134.17(1986 edition) and Westinghouse's Appendix B Program. Since the construction of the VCSNS replacement steam generators, Westinghouse has closed the fabrication facility and has not yet located the supporting documentation for this item. It is anticipated that the information will be located and submitted to the NRC in August 2012.flaw evaluation to show adequate thickness against stress corrosion cracking.[VCSNS Response]Westinghouse LTR-PAFM-12-86-NP, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements has been provided as Attachment 1 of this enclosure.
Based on the Pressurized Water Stress Corrosion Cracking (PWSCC) crack growth analysis results, the service life required to grow through the Alloy 152 weld inlay is more than 10 effective full power years. This service life is more than the required examination interval of 10 years for Inspection Item G, "Uncracked butt weld mitigated with an inlay" in accordance with Code Case N-770-1.for primary water stress corrosion crack growth rates for Alloy 52/152 weld 12 materials, at this time, NRC recommends using the Alloy 182 crack growth rate curve provided in MRP-1 15, with an improvement factor (IF) of 100 for Alloy 52 welds and an IF of 10 for Alloy 152 welds.[VCSNS Response]Westinghouse LTR-PAFM-12-86-NP, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements has been provided as Attachment 1 of this enclosure.
For PWSCC, the crack growth model for Alloy 152 weld inlay material is based on that given in MRP-1 15 for Alloy 182 weld material with an improvement factor of 100. This improvement factor, although higher than the recommended in the public question response shown in Appendix A, is a more accurate improvement factor for Alloy 152 weld based on the reported data documented in NUREG/CR-7103 as well as those from GE Global Research.
Document Control Desk Enclosure 1 CR-12-00556 RC-12-0110 Page 4 of 5 6. Duration of Proposed Alternative This request for an alternative categorization for Steam Generator Nozzles (Hot and Cold Leg) to Safe End Welds will be a permanent change to the program for the duration of the operating license and license renewal. The Facility Operating License (NPF-12) was issued August 6, 1982 and was superseded by Renewed Facility Operating License issued on April 23, 2004. VCSNS is in the last period of its third 10 year inservice inspection (ISI) interval that will end December 31, 2013.Per 10CFR50.55a(g)(6)(ii)(F)(3), the baseline examination shall be completed by the end of the next refueling outage after January 20, 2012. VCSNS is also requesting relief under this letter as documented within Enclosure 2, RR-111-08 to delay the baseline examination to 2014 (RF21). The one time deferral proposed herein extends the inservice inspection interval beyond the current third interval end date.7. Precedents None.8. References Proprietary documents may be viewed at the Westinghouse Rockville, MD. office.1. 10CFR50-55a, Codes and Standards 2. FR36232 Volume 76, Number 119, issued June 21, rulemaking change to 10CFR50.55a
- 3. Public Meeting Summary ASME N-770-1 [ML112240818]
- 4. Virgil C. Summer Nuclear Station -Relief Request (RR-II-07)
Associated with the Risk-Informed Inservice Inspection (RI-ISI) Program (TAC NO. MB6523)[ML031320443]
- 5. ASME CODE CASE N-770-1 6. ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition through 2000 Addenda, American Society of Mechanical Engineers, New York 7. EPRI 1010087 MRP-139 8. VCSNS Drawings [PROPRIETARY]
- a. 1MS-07-400-0001, Machining and Assembly -Channel Head Welding (6145E22)b. 1MS-07-400-0003, Primary Nozzle -Channel Head Welding (6145E22)c. 1 MS-07-400-0004, Nozzle Safe End Weld -Channel Head Welding (6145E22)
Document Control Desk Enclosure 1 CR-12-00556 RC-12-0110 Page 5 of 5 d. 1MS-07-400-0005, Safe End Final Machining
-Channel Head Welding (6145E22)e. 1MS-07-400-0007, General Notes -Channel Head Welding (6145E22)9. Westinghouse LTR-SGDA-12-27
[PROPRIETARY], V. C. Summer Unit 1 Replacement Steam Generators
-Manufacturing Records for Channel Head Primary Inlet/Outlet Nozzle to Safe End Welds, Dated June 18, 2012 10. Westinghouse LTR-PAFM-12-86-NP, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements, Dated July 2012