|
---|
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
[Table view] |
Text
Thomas D. Gatlin Vice President,Nuclear Operations SCEi m Gm 803.345.4342 A SCANA COMPANY January 20, 2015 RC-15-0009 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 RELIEF REQUEST RR-4-07 REQUEST TO USE ALTERNATIVE ROOT MEAN SQUARE (RMS) DEPTH SIZING REQUIREMENTS
Reference:
- 1. Letter from J. Archie (VCSNS) to Document Control Desk (NRC),
"Request to Use Alternatives to ASME Code Requirements.in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)," dated June 20, 2006 (ML061720495]
- 2. Letter from J. Archie (VCSNS) to Document Control.Desk (NRC),
"Supplemental Information Regarding Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice.Inspection Interval (RR-III-03, RR-III-04)," dated October 19, 2006
[ML062990461]
- 3. NRC Letter to J. Archie (VCSNS), "Virgil C. Summer Nuclear Station, Unit NO.1 - Relief Requests RR-111-03 and RR-III-04 (TAC NO.
MD2422)," dated November 21, 2006 [ML063070540]:
South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service Authority, hereby submits a request for relief.. In accordance with 10CFR50.55a(z)(1), SCE&G is requesting relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components" in that proposed alternatives would provide an acceptable level of quality and safety.
Specifically, this relief request proposes to use a root. mean square error criterion for sizing flaws that is greater than that allowed by ASME Code for Reactor Pressure Vessel (RPV) nozzles to safe-end cold leg welds. This relief request is similar to relief requests that VCSNS previously submitted for the Third Inservice Inspection Interval (References 1 & 2) that were approved by the NRC in Reference 3 for RPV to safe-end hot leg welds.
ý Virgil C.Summer Station *Post Office Box 88. Jenkinsville, SC .29065. F(803) 941-9776
Document Control Desk CR-14-06288 RC-1 5-0009 Page 2 of 2 SCE&G requests that this repair alternative be approved by October 1, 2015, in support of the upcoming Fall 2015 refueling outage (RF22).
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 WLT/TDG/
Enclosure:
VCSNS Relief Request RR-4-07 c: K. B. Marsh S. A. Byrne J. B. Archie N. S. Carns J. H. Hamilton J. W. Williams W. M. Cherry V. M. McCree S. A. Williams NRC Resident Inspector K. M. Sutton NSRC RTS (CR-14-06288)
File (810.19)
PRSF (RC-1 5-0009)
Document Control Desk Enclosure CR-14-06288 RC-1 5-0009 Page 1 of 4 South Carolina Electric & Gas Co. (SCE&G)
Virgil C. Summer Nuclear Station Unit I (VCSNS)
VCSNS Relief Request RR-4-07
- 1. ASME Code Component(s) Affected The affected VCSNS components are the Class 1, Code Case N-770-1, Inspection Item B, Unmitigated butt weld at Cold Leg operating temperature. The affected welds are:
1-4100A-15 (DM) A "A" Loop Inlet Safe-End Elbow 1-4200A-15 (DM) B "B" Loop Inlet Safe-End Elbow 1-4300A-15 (DM) C "C" Loop Inlet Safe-End Elbow 1-4100A-16 (DM) A "A" Inlet Nozzle to Safe-End 1-4200A-16 (DM) B "B" Inlet Nozzle to Safe-End 1-4300A-16 (DM) C "C" Inlet Nozzle to Safe-End
- 2. Applicable Code Edition and Addenda ASME Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2007 Edition with 2008 Addenda. Testing of personnel, procedures, and equipment for the ultrasonic examination of applicable Class 1 components is governed by Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the ASME Code, Section Xl.
- 3. Applicable Code Requirement The examination of Class 1 and 2 piping welds are required to be performed using procedures, personnel and equipment qualified to the criteria of the ASME Code, Section Xl, Appendix VIII, and specifically Supplement 10, "Qualification Requirements for Dissimilar Metal Pipe Welds," for the examination of nozzle-to-piping dissimilar metal welds.
Paragraph 3.3, "Depth Sizing Test," Subparagraph (c) of Supplement 10 states "examination procedures, equipment, and personnel are qualified for depth sizing when the RMS (root mean square) error of the flaw depth measurements, as compared to the true flaw depths, is less than or equal to 0.125-inch (3 mm)."
- 4. Reason for Request VCSNS is performing an ultrasonic re-examination of the indicated welds from the inside diameter (ID) surface during the upcoming refueling outage as required by Code Case N-770-1.
Document Control Desk Enclosure CR-14-06288 RC-1 5-0009 Page 2 of 4 VCSNS proposes using an alternative RMS error depth-sizing requirement as compared to the 0.125 inches RMS error value stated in ASME Code,Section XI, Appendix VIII, Supplement 10, Paragraph 3.3, Subparagraph (c). To date, no vendor has been capable of meeting this criterion.
- 5. Proposed Alternative and Basis for Use 5.1 Proposed Alternative SCE&G proposes to use ASME Code, Section Xl, Appendix VIII, Supplement 10, Paragraph 3.3 with a root mean square error (RMSE) of 0.189 inches instead of the 0.125 inches specified for depth sizing in the Code. In the event that an indication is detected and requires depth sizing, the 0.064 inches difference between the required RMSE and the demonstrated RMSE (0.189-0.125 = 0.064) will be added to the measured through wall extent for comparison to the applicable acceptance standard.
Should the contracted vendor demonstrate an improved depth sizing RMSE prior to the performance of these examinations, the difference of that improved RMSE will be substituted for the 0.189 inches.
5.2 Technical Basis for Proposed Alternative ASME Code Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2007 Edition with 2008 Addenda as approved by 10 CFR 50.55a. To date, although examination vendors have qualified for detection and length sizing on these welds, these examination vendors have not met the established RMSE requirement for depth sizing. The contracted vendor for SCE&G has demonstrated the ability to meet the depth sizing qualification requirement with a RMSE of 0.189 inches instead of the 0.125 inches established by the Code Case.
The addition of the difference in allowable depth sizing tolerance from that actually demonstrated to the flaw depths measured will compensate for the possible variance in measured depth.
Document Control Desk Enclosure CR-14-06288 RC-1 5-0009 Page 3 of 4 5.3 Safety Evaluation Compliance The proposed alternative assures that the indicated welds will be fully examined by procedures, personnel and equipment qualified by demonstration in all aspects except depth sizing. In order to compensate for the depth sizing, the addition of the difference between the qualified and demonstrated sizing tolerance will provide an acceptable level of safety and quality in accordance with 10 CFR 50.55a(z)(1). The proposed alternative has been previously approved for VCSNS via NRC Letter dated November 21, 2006, (TAC NO.
MD2422) [ML063070540].
- 6. Duration of Proposed Alternative This relief request will be implemented during the VCSNS fourth ISI interval, which commenced on January 1, 2014 and ends on December 31, 2023.
This is a new relief request based on ASME Code,Section XI, Appendix VIII, Supplement 10, and the examination vendors' most accurate demonstrated depth sizing performance.
- 7. Precedents Requests to use an alternative RMSE value have been previously approved by the NRC. In Reference 3, the NRC previously approved the proposed alternative RMSE relief request submitted by VCSNS in References 1 and 2 for hot leg welds. The NRC approved a similar alternative for Point Beach Unit 1 hot leg welds in Reference 6.
Document Control Desk Enclosure CR-14-06288 RC-1 5-0009 Page 4 of 4
- 8. References
- 1. Letter from J. Archie (VCSNS) to Document Control Desk (NRC), "Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)," dated June 20, 2006
[ML061720495]
- 2. Letter from J. Archie (VCSNS) to Document Control Desk (NRC),
"Supplemental Information Regarding Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)," dated October 19, 2006 [ML062990461]
- 3. NRC Letter to J. Archie (VCSNS), "Virgil C. Summer Nuclear Station, Unit NO.1 - Relief Requests RR-111-03 and RR-111-04 (TAC NO. MD2422)," dated November 21, 2006 [ML063070540]
- 4. Letter from L. Meyer (NextEra Energy - Point Beach Nuclear Plant, Unit 1) to Document Control Desk (NRC), "10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the 'A' Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval," dated November 9, 2012 [ML12318A125]
- 5. Letter from L. Meyer (NextEra Energy - Point Beach Nuclear Plant, Unit 1) to Document Control Desk (NRC), "Supplement to 10 CFR 50.55a Request, Relief Request 1 -RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the 'A' Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval," dated December 14, 2012 [ML12349A364]
- 6. Letter from L. Meyer (NextEra Energy - Point Beach Nuclear Plant, Unit 1) to Document Control Desk (NRC), "10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the 'A' Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval Response to Request for Additional Information," dated February 1, 2013 [ML13035A018]
- 7. NRC Letter to L. Meyer (NextEra Energy ), "Point Beach Nuclear Plant, Unit 1 - Relief Request 1-RR-4 re: Re-Examination of the Unit 1 RPV Indication on the 'A' Inlet Nozzle Weld (TAC No. ME9905)," dated March 18, 2013
[ML13064A425]