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Category:Letter type:L
MONTHYEARL-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024
License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References
L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024
Twenty-Ninth Refueling Outage Inservice Inspection Summary Report
L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024
Submittal of Quality Assurance Program Manual, Revision 30
L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024
Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models
L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024
BV-2, Post Accident Monitor Report
L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024
Reactor Vessel Surveillance Capsule Withdrawal Schedule
L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024
Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations
L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024
Cycle 30 Core Operating Limits Report
L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024
CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair
L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024
Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)
L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024
Emergency Preparedness Plan
L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024
L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024
Withdrawal of Exemption Request
L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024
Annual Notification of Property Insurance Coverage
L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024
Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule
L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023
Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023
Submittal of the Updated Final Safety Analysis Report, Revision 27
L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023
Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023
L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023
Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615
L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023
Twenty-Third Refueling Outage Inservice Inspection Summary Report
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023
Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615
L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023
Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023
Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological
L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023
Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023
180-Day Steam Generator Tube Inspection Report
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023
Report of Facility Changes, Tests and Experiments
L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023
Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
2024-09-17
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TM Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Paul A. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 July 11, 2012 L-12-204 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Containment Liner Random and Non-Random Examinations Report In accordance with license renewal commitment 34 described by FirstEnergy Nuclear Operating Company (FENOC) in correspondence dated September 14, 2009 and confirmed by the Nuclear Regulatory Commission (NRC) in NUREG-1929, Appendix A, enclosed is the Containment Liner Random and Non-Random Examinations Report for the Beaver Valley Power Station, Unit No.1 (BVPS-1) spring 2012 refueling outage (1 R21)"
By letter dated February 14, 2011, FENOC submitted the Containment Liner Random and Non-Random Examinations Report for the BVPS-1 fall 2010 refueling outage (1 R20). Random and non-random containment liner examination activities performed during 1R20 and 1R21 that are associated with BVPS-1 license renewal commitments 32 and 33 listed in NUREG-1929 have been satisfactorily completed and documented in correspondence to the NRC. Therefore, license renewal commitments 32, 33, and 34 are considered closed.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor-Fleet Licensing, at 330-315-6808.
Beaver Valley Power Station, Unit No.1 L-12-204 Page 2 of 2
Enclosure:
1R21 Containment Liner Random and Non-Random Examinations Report cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-12-204 1R21 Containment Liner Random and Non-Random Examinations Report (4 Pages Follow)
lR21 CONTAINMENT LINER RANDOM AND NON-RANDOM EXAMINATIONS REPORT TABLE OF CONTENTS Page Number Table of Contents 1 Examination Summary 2 Appendix I - Summary of Random Exams 1 page
EXAMINATION
SUMMARY
Supplemental volumetric examinations were performed on the Beaver Valley Power Station, Unit No.1 (BVPS-1) containment liner prior to and during the twenty-first refueling outage (1R21) in the spring of2012 to satisfy BVPS-1license commitment 32.
This commitment is listed in BVPS-1 Updated Final Safety Analysis Report Table 16-1.
The non-random examinations that satisfied license renewal commitment 33 were performed during the twentieth refueling outage (1 R20) in the fall of 20 10. A summary of the commitment is as follows:
License Commitment 32:
Supplemental volumetric examinations will be performed on the BVPS-1 containment liner prior to the period of extended operation. A minimum of seventy-five randomly selected (as described in First Energy Nuclear Operating Company Letter L-09-205) locations will be examined (as described in FENOC Letter L-09-243). If degradation is identified, it will be addressed through the corrective action program (as described in FENOC Letter L-09-243).
If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the random samples examined using ultrasonic testing (UT), UT examinations shall be performed on additional random samples, to ensure a 95 percent confidence that 95 percent of the unexamined accessible containment liner is not degraded. If additional degradation is identified, the sample size for the UT examinations shall be further expanded until the statistical sampling has achieved the 95 percent confidence goal described previously. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.
The initial BVPS-1 sample lot of a minimum of 75 random ultrasonic examinations will be completed in the next three refueling outages, beginning with the BVPS-1 refueling outage in 2010. The entire sample plan (including additional examinations, if required) will be completed by January 29, 2016.
Summary of Random Scope Examinations:
Thirty-seven of the seventy-five randomly selected examinations were examined during the BVPS-1 1R21 refueling outage as part of the sample plan and were completed with no evidence of loss of material. Thirty-eight random examinations were previously completed during 1R20 with no evidence of loss of material. Based on the 1R20 and 1R21 random examination results, a 95 percent confidence has been achieved that 95 percent of the unexamined accessible containment liner is not degraded. Since there was no evidence of degradation, no additional sampling or successive re-examinations were required.
2
The acceptance criterion for the examinations had been established as 90 percent of the nominal wall thickness (that is, 0.337 inches for the vertical shell and 0.450 inches for the dome). Appendix I contains the 1R21 random examinations results.
Previously Completed Examinations:
Eight examinations at non-random locations were performed during 1R20. Two examinations at non-random locations were completed prior to the outage, in May 2010.
The locations selected included irregular contours of the liner, repainted areas of the liner, areas adjacent to the discovered through-wall hole, the below-grade area between elevations 725 feet and 735 feet, and the area below the 2006 steam generator replacement opening. Acceptance criterion for the examinations is 90 percent of the nominal wall thickness (0.337 inches). All 10 locations examined online and during 1R20 were completed with no evidence of loss of material. Since there was no evidence of degradation, no additional sampling or successive re-examinations were required.
3
APPENDIX I 1R21 COMPELETED RANDOM EXAMS Acceptance Component ID Re~ort No. Lowest Highest General Criteria 1RN-01 UT-12-1117 0.541" 0.554" 0.546" 0.450" 1RN-02 UT-12-1093 0.512" 0.528" 0.528" 0.450" 1RN-03 UT-12-1094 0.548" 0.558" 0.55ft 0.450" 1RN-04 UT-12-1115 0.495" 0.516" 0.508" 0.450" 1RN-05 UT-12-1116 0.480" 0.516" 0.504" 0.450" 1RN-06 UT-12-1092 0.513" 0.524" 0.518" 0.450" 1RN-07 UT-12-1114 0.507" 0.517" 0.512" 0.450" 1RN-08 UT-12-1113 0.500" 0.519" 0.513" 0.450" 1RN-09 UT-12-1112 0.501" 0.518" 0.507" 0.450" 1RN-10 UT-12-1069 0.504" 0.532" 0.515" 0.450" 1RN-11 UT-12-1076 0.502" 0.524" 0.511" 0.450" 1RN-12 UT-12-1070 0.499" 0.526" 0.505" 0.450" 1RN-13 UT-12-1077 0.535" 0.592" 0.575" 0.450" 1RN-14 UT-12-1096 0.501" 0.514" 0.505" 0.450" 1RN-15 UT-12-1095 0.547" 0.568" 0.559" 0.450" 1RN-16 UT-12-1078 0.521" 0.548" 0.540" 0.450" 1RN-17 UT-12-1079 0.531" 0.553" 0.547" 0.450" 1RN-18 UT-12-1080 0.532" 0.548" 0.538" 0.450" 1RN-19 UT-12-1081 0.535" 0.548" 0.541" 0.450" 1RN-21 UT-12-1075 0.531" 0.551" 0.538" 0.450" 1RN-22 UT-12-1072 0.519" 0.551" 0.532" 0.450" 1RN-23 UT-12-1071 0.525" 0.552" 0.530" 0.450" 1RN-24 UT-12-1065 0.514" 0.537" 0.520" 0.450" 1RN-27 UT-12-1099 0.522" 0.548" 0.530" 0.450" 1RN-28 UT-12-1100 0.488" 0.514" 0.495" 0.450" 1RN-32 UT-12-1087 0.378" 0.399" 0.388" 0.337" 1RN-33 UT-12-1088 0.397" 0.443" 0.414" 0.337" 1RN-35 UT-12-1091 0.397" 0.428" 0.415" 0.337" 1RN-38 UT-12-1067 0.392" 0.412" 0.404" 0.337" 1RN-43 UT-12-1023 0.355" 0.426" 0.409" 0.337" 1RN-44 UT-12-1084 0.390" 0.431" 0.411" 0.337" 1RN-45 UT-12-1063 0.391" 0.451" 0.420" 0.337" 1RN-46 UT-12-1064 0.402" 0.415" 0.410" 0.337" 1RN-49 UT-12-1066 0.421" 0.426" 0.424" 0.337" 1RN-51 UT-12-1083 0.401" 0.435" 0.417" 0.337" 1RN-61 UT-12-1001 0.418" 0.445" 0.428" 0.337" 1RN-66 UT-12-1082 0.409" 0.430" 0.418" 0.337"