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| | ELECTRIC POWER RESEARCH INSTITUTE 2018-112 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.BWR Vessel & Internals Project (BWRVIP) |
| | August 29, 2018 Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike ' |
| | Rockville, MD 20852 BWRVIP Docket No. 99902016 |
| | |
| | ==Subject:== |
| | BWRVIP-319NP: BWR Vessel and Internals Project, Testing and Evaluation of the Hatch Unit 2 120° Surveillance Capsule |
| | |
| | ==References:== |
| | : 1. M. Markley to A. McGehee and J. Hutto, "Edwin I. Hatch Nuclear Plant, Unit No. 2 -Request for Extension of Date to Submit Reactor Vessel Surveillance Capsule Summary Technical Report (CAC No. MF9753; EPID L-2017-LLL-0011)," January 22, 2018. |
| | Enclosed is one (1) paper copy of the report "BWRVIP-319NP: BWR Vessel and Internals Project, Testing and Evaluation of the Hatch Unit 2 120° Surveillance Capsule," EPRI Technical Report 3002013103, August 2018. This report is being transmitted to the NRC for information only. |
| | This report describes testing and evaluation of the Hatch Unit 2 120° surveillance capsule. These results will be used to monitor embrittlement as part of the BWRVIP Integrated Surveillance Program (ISP). |
| | * The weld material in the Hatch Unit 2 120° surveillance capsule is identified in BWRVIP-86, Revision 1-A, as representative for target materials for target weld materials in the Hatch Unit 2, Nine Mile Point Unit 1, and Oyster Creek reactor vessels. |
| | However, the weld material in the Hatch Unit 2 120° is not'a heat-specific match to any of the target weld materials. Therefore, the surveillance data will not be used directly. |
| | * The plate material in the Hatch Unit 2 120° surveillance capsule is identified in BWRVIP-86, Revision 1-A, as representative for target plate material for the Hatch Unit 2 reactor vessel only. The plate representative material in the 120°capsule is not a heat specific match to the target plate material in the Hatch Unit 2 reactor vessel. However, the representative material is a heat-specific match to another plate material in the Hatch Unit 2 reactor vessel and direct use will be made of the sul:"Veillance data. The Hatch Unit 2 P-T limit curves are contained in a Pressure-Temperature Limits Report (PTLR) and Together ... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillview Avenue, Palo Alto, CA 9430,i-1395 USA* 650.855.2000 |
| | * Customer Service 800.313.3774 |
| | * www.epri.com |
| | |
| | the impact of the test results from the 120° surveillance capsule are currently being evaluated. |
| | It should be noted that the BWRVIP previously requested an extension to the 10 CFR 50 Appendix H surveillance capsule testing reporting requirements and committed to providing the results of the Hatch Unit 2 120° surveillance capsule by August 31, 2018. That request was approved in Reference 1. |
| | Please also note that the enclosed report is non-proprietary and is available to the public by request to EPRI. |
| | If you have any questions on this subject please call Steve Richter (Energy Northwest, BWRVIP Assessment Committee Chairman) at 509-377-4703. |
| | Sincerely, Andrew McGehee, EPRI, BWRVIP Chairman Tim Hanley, Exelon Corporation, BWRVIP Chairman c: D. Alley, NRC-NRR M. Kirk, NRC-RES D. Odell, Exelon Corp. |
| | R. Carter, EPRI A. McGehee, EPRI}} |
|
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Category:Letter
MONTHYEARIR 05000321/20240102024-11-0606 November 2024 NRC Inspection Report 05000321/2024010 and 05000366/2024010 ML24299A2222024-10-31031 October 2024 Audit Summary for License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components IR 05000321/20240032024-10-30030 October 2024 Edwin I Hatch, Units 1 and 2 - Integrated Inspection Report 05000321/2024003 and 05000366/2024003 NL-24-0357, Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines2024-10-30030 October 2024 Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines ML24292A1602024-10-22022 October 2024 Request for Withholding Information from Public Disclosure License Amendment Request to Revise Technical Specification Surveillance Requirements to Increase Safety/Relief Valve Setpoints ML24290A0792024-10-18018 October 2024 SLR Environmental Preapplication Meeting Summary ML24303A4102024-10-17017 October 2024 Dir Results Letter to NRC - Hatch - Hurricane Helene IR 05000321/20244012024-10-10010 October 2024 Security Baseline Inspection Report 05000321-2024401 and 05000366-2024401 ML24256A0282024-09-12012 September 2024 2024 Hatch Requal Inspection Corporate Notification Letter NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc IR 05000321/20240912024-08-27027 August 2024 NRC Investigation Report 2-2023-003 and NOV - NRC Inspection Report 05000321/2024091 and 05000366/2024091 IR 05000321/20240052024-08-26026 August 2024 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Report 05000321/2024005 and 05000366/2024005 NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information IR 05000321/20240022024-08-0808 August 2024 Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24198A1252024-07-16016 July 2024 Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 05000321/LER-2024-002-01, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024 Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications 05000321/LER-2024-003, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024 Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 ML24163A0532024-06-14014 June 2024 Audit Plan - Alternative Seismic Method LAR NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations IR 05000321/20240902024-05-15015 May 2024 NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024 Manual Reactor Trip Due to Loss of Feedwater NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 IR 05000032/20240112024-04-25025 April 2024 Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 ML23032A3322024-04-24024 April 2024 Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes 05000366/LER-2024-002, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024 Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications IR 05000321/20240012024-04-22022 April 2024 Integrated Inspection Report 05000321/2024001 and 05000366/2024001 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint 05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-0909 April 2024 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML23275A2402024-03-22022 March 2024 SNC Fleet - Issuance of Environmental Assessment and Finding of No Significant Impact Regarding Exemption from the Requirements of 10 CFR Part 73, Section 73.2, Definitions (EPID Nos. L-2023-LLE-0018 & L-2023-LLE-0021) - Letter NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) ML24047A0362024-03-0404 March 2024 Response to Hatch and Vogtle FOF Dates Change Request (2025) NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 2024-09-09
[Table view] |
Text
r.:::::1!!~~11
~*-*~
ELECTRIC POWER RESEARCH INSTITUTE 2018-112 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.BWR Vessel & Internals Project (BWRVIP)
August 29, 2018 Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike '
Rockville, MD 20852 BWRVIP Docket No. 99902016
Subject:
BWRVIP-319NP: BWR Vessel and Internals Project, Testing and Evaluation of the Hatch Unit 2 120° Surveillance Capsule
References:
- 1. M. Markley to A. McGehee and J. Hutto, "Edwin I. Hatch Nuclear Plant, Unit No. 2 -Request for Extension of Date to Submit Reactor Vessel Surveillance Capsule Summary Technical Report (CAC No. MF9753; EPID L-2017-LLL-0011)," January 22, 2018.
Enclosed is one (1) paper copy of the report "BWRVIP-319NP: BWR Vessel and Internals Project, Testing and Evaluation of the Hatch Unit 2 120° Surveillance Capsule," EPRI Technical Report 3002013103, August 2018. This report is being transmitted to the NRC for information only.
This report describes testing and evaluation of the Hatch Unit 2 120° surveillance capsule. These results will be used to monitor embrittlement as part of the BWRVIP Integrated Surveillance Program (ISP).
- The weld material in the Hatch Unit 2 120° surveillance capsule is identified in BWRVIP-86, Revision 1-A, as representative for target materials for target weld materials in the Hatch Unit 2, Nine Mile Point Unit 1, and Oyster Creek reactor vessels.
However, the weld material in the Hatch Unit 2 120° is not'a heat-specific match to any of the target weld materials. Therefore, the surveillance data will not be used directly.
- The plate material in the Hatch Unit 2 120° surveillance capsule is identified in BWRVIP-86, Revision 1-A, as representative for target plate material for the Hatch Unit 2 reactor vessel only. The plate representative material in the 120°capsule is not a heat specific match to the target plate material in the Hatch Unit 2 reactor vessel. However, the representative material is a heat-specific match to another plate material in the Hatch Unit 2 reactor vessel and direct use will be made of the sul:"Veillance data. The Hatch Unit 2 P-T limit curves are contained in a Pressure-Temperature Limits Report (PTLR) and Together ... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillview Avenue, Palo Alto, CA 9430,i-1395 USA* 650.855.2000
- Customer Service 800.313.3774
the impact of the test results from the 120° surveillance capsule are currently being evaluated.
It should be noted that the BWRVIP previously requested an extension to the 10 CFR 50 Appendix H surveillance capsule testing reporting requirements and committed to providing the results of the Hatch Unit 2 120° surveillance capsule by August 31, 2018. That request was approved in Reference 1.
Please also note that the enclosed report is non-proprietary and is available to the public by request to EPRI.
If you have any questions on this subject please call Steve Richter (Energy Northwest, BWRVIP Assessment Committee Chairman) at 509-377-4703.
Sincerely, Andrew McGehee, EPRI, BWRVIP Chairman Tim Hanley, Exelon Corporation, BWRVIP Chairman c: D. Alley, NRC-NRR M. Kirk, NRC-RES D. Odell, Exelon Corp.
R. Carter, EPRI A. McGehee, EPRI