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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
Stephen A. Byrne Senior Vice President,Nuclear Operations 803.345.4622 May 13, 2002 A SCANA COMPANY RC-02-0093 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 RELIEF REQUEST FOR UTILIZATION OF CODE CASE N-597 South Carolina Electric & Gas Company (SCE&G) is requesting approval for relief from the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition, (no addenda), the In-service Inspection Code of Record (Code of Record) for VCSNS. This relief would allow code case N-597 to be used for determining the structural integrity of components degraded by wall thinning as a result of flow accelerated corrosion.
The description of this alternative, including justification, is included as an attachment to this letter. SCE&G requests NRC review and approval of this request by 5/22/02 so that VCSNS can complete an evaluation of wall thinning identified in a feedwater pipe elbow. This component is the first 18" 90 degree elbow located downstream of feedwater flow control valve IFV00498-FW (Loop "C"). VCSNS is currently shutdown for its 1 3 th refueling outage. This issue must be resolved prior to startup. Replacing the elbow at this time would have a severe impact on the outage schedule due to the complexity of such an emergent task. The job could not be performed within our current window of opportunity. The overall length of the outage would therefore be extended accordingly. The wear rate evaluation shows that the elbow will be acceptable for another cycle using the N-597 methodology. Replacement of this elbow is currently scheduled for the next refueling outage utilizing improved materials not readily available on a short notice basis.
SCE&G is submitting the attached relief request in accordance with 10CFR50.55a(a)(3)(i) and a(a)(3)(ii).
SCE&G I Virgil C.Summer Nuclear Station - P.0.Box 88 . Jenkinsville, South Carolina 29065 . T(803) 345.5209
Document Control Desk NRR 02-1518 RC-02-0093 Page 2 of 2 Should you have any questions, please call Mr. Robert Sweet at (803) 345-4080.
Very truly yours, Stephen A. Byrne RGS/SAB/dr Attachment c: N. 0. Lorick N. S. Cams T. G. Eppink (w/o Attachment)
R. J. White L. A. Reyes K. R. Cotton NRC Resident Inspector K. M. Sutton RTS (NRR 02-1518)
File (810.19-2)
DMS (RC-02-0093)
NUCLEAR EXCELLENCE - A SUMMER TRADITION!
Document Control Desk Attachment NRR 02-1518 RC-02-0093 Page 1 of 2 South Carolina Electric & Gas Co. (SCE&G)
Virgil C. Summer Nuclear Station (VCSNS)
Relief Request
Subject:
VCSNS desires to incorporate Code Case N-597 into the program used for determining the structural integrity of components degraded by flow-accelerated corrosion.
Components:
System: Miscellaneous safety related and quality related piping systems.
Components: Carbon and low-alloy steel piping components monitored for flow accelerated corrosion.
ISI Class: 2 and 3.
Current Code Requirement:
ASME B&PV Code Section Xl (IWA-3100) provides the process for the disposition of flaw examination evaluations that exceed the acceptance standards for materials and welds specified in the Code applicable to the construction of the component. This provision stipulates that the disposition shall be subjected to review by the regulatory and enforcement authorities having jurisdiction at the plant site.
Alternative Requirement:
As an alternative to the requirements of IWA-31 00, "Evaluation," the VCSNS proposes to use the provisions of ASME B&PV Code Case N-597 for the analytical evaluation of Class 2 and 3 carbon and low-alloy steel piping items subjected to wall thinning as a result of flow-accelerated corrosion rather than to repair the component if the construction code minimum wall thickness has been reached. This Code case stipulates that the methods of predicting the rate of wall thickness loss and the predicted remaining wall thickness shall be the responsibility of the owner. VCSNS has procedural controls in the Flow-Accelerated Corrosion (FAC) Program that provide direction for calculating wear rates, forecasting remaining life, and conducting inspections of piping components susceptible to FAC. The methodology is consistent
Document Control Desk Attachment NRR 02-1518 RC-02-0093 Page 2 of 2 with industry standard NSAC-202L-R2, "Recommendations for an Effective Flow Accelerated Corrosion Program," for calculating wear rates, forecasting remaining life, and conducting inspections as programmatic requirements. In the VCSNS program, the terms "should" and "shall" are treated as follows:
"Shall" indicates a mandatory requirement.
"Should" indicates a non-mandatory requirement, but is considered the preferred method to comply with a specific requirement, unless otherwise determined by engineering support personnel or management.
These terms are defined in procedure ES 421, Flow-accelerated Corrosion Program.
Basis for Request:
Code Case N-597, Requirements for Analytical Evaluation of Pipe Wall Thinning,Section XI, Division I, provides an acceptable approach for determining the structural integrity of components degraded as a result of flow-accelerated or other corrosion phenomena. The methodology specified in the code case is sufficiently conservative, and thus provides an adequate margin of safety for evaluating a component's structural integrity. Maintaining the option of using Code Case N-597 will facilitate the scheduling of the replacement of components degraded by wall thinning as a result of flow accelerated corrosion.
The NRC has previously approved the use of Code Case N-597 for Hope Creek and Salem Nuclear Generating Stations in a letter dated October 12, 2000 (TAC Nos.
MA8595, MA8600 and MA8601).
Approval to use Code Case N-597 was also granted to Surry Power Station units 1 and 2 and North Anna Power Station Units 1 and 2 in a letter dated September 10, 2001 (TAC Numbers MB2276, MB2277, MB2223, and MB2284). Note also that VCSNS has the same code of record as North Anna Unit 1 and Surry Units 1 and 2.
Implementation Schedule Upon NRC approval, the proposed alternative, i.e., Code Case N-597, will be implemented immediately.
