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Category:Letter
MONTHYEARML24025A0922024-01-25025 January 2024
Requalification Program Inspection
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
IR 05000334/20230112023-12-0404 December 2023
Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011
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
IR 05000334/20233012023-11-27027 November 2023
Initial Operator Licensing Examination Report 05000334/2023301
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
IR 05000334/20230032023-11-0606 November 2023
Integrated Inspection Report 05000334/2023003 and 05000412/2023003
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
ML23279A0612023-10-0505 October 2023
Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23198A3592023-10-0202 October 2023
Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary
IR 05000334/20234022023-09-29029 September 2023
Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only)
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000334/20234012023-09-21021 September 2023
Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only)
ML23263A0192023-09-20020 September 2023
Operator Licensing Examination Approval
ML23243A9272023-09-19019 September 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
ML23249A1842023-09-18018 September 2023
Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06
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
IR 05000334/20230052023-08-31031 August 2023
Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005)
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000334/20230022023-08-0909 August 2023
Integrated Inspection Report 05000334/2023002 and 05000412/2023002
ML23219A0592023-08-0707 August 2023
Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage
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
ML23188A0982023-07-17017 July 2023
Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML23188A0672023-07-10010 July 2023
Project Manager Assignment
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
ML23157A1072023-06-0707 June 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011
ML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023
Submittal of the Updated Final Safety Analysis Report, Revision 34
ML23102A1472023-05-22022 May 2023
Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23135A7872023-05-19019 May 2023
Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
ML23124A3882023-05-16016 May 2023
Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
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
IR 05000334/20230012023-05-0808 May 2023
Integrated Inspection Report 05000334/2023001 and 05000412/2023001
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
ML23118A3812023-04-28028 April 2023
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
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23107A2502023-04-18018 April 2023
Requalification Program Inspection
2024-01-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 10, 2011 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.2 - STAFF EVAULATION REGARDING THE 2009 STEAM GENERATOR INSPECTION REPORT (TAC NO. ME3998)
Dear Mr. Harden:
By letter dated February 11, 2010, as supplemented by letters dated May 17, 2010, and January 14, 2011, FirstEnergy Nuclear Operating Company, (the licensee) submitted information summarizing the results of the 2009 steam generator (SG) tube inspections for the 14th refueling outage at Beaver Valley Power Station, Unit No.2 (BVPS-2), in accordance with Technical Specification (TS) 5.6.6.2.4.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and has concluded that the licensee provided the information required by their TSs and that no additional follow-up is required at this time. The NRC staff's review of the report is enclosed.
Please contact me at (301) 415-1016, if you have any questions regarding this issue.
Sincerely,
./7
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",,/
Nadiyah S. Morgan, Project Manager Plant licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
As stated cc w/encl: Distribution via listserv
STAFF EVALUATION REGARDING THE 2009 STEAM GENERATOR TUBE REPORT BEAVER VALLEY POWER STATION. UNIT NO.2 DOCKET NUMBER 50-412 By letter dated February 11, 2010, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100491087), as supplemented by letters dated May 17, 2010 (ADAMS Accession No. ML101410292), and January 14, 2011 (ADAMS Accession No. ML110200067), FirstEnergy Nuclear Operating Company, (the licensee) submitted information summarizing the results of the 2009 steam generator (SG) tube inspections for the 14th refueling outage at Beaver Valley Power Station, Unit No.2 (BVPS-2), in accordance with Technical Specification (TS) 5.6.6.2.4. In addition to this report, the U.S. Nuclear Regulatory Commission (NRC) staff summarized the October 23, 2009, conference call regarding the ongoing 2009 SG tube inspection activities at BVPS-2 by letter dated November 18,2009 (ADAMS Accession No. ML093140728).
BVPS-2 is a 3-loop plant with Westinghouse model 51 SGs. Each SG contains 3,376 mill annealed Alloy 600 tubes. Each tube has a nominal outside diameter (00) of 0.875-inch and a nominal wall thickness of 0.050-inch. The tubes are supported by a number of carbon steel tube support plates and Alloy 600 anti-vibration bars. The tubes were roll expanded at both ends for the full length of the tubesheet. The entire length of tube within the tubesheet was shot-peened on both the hot and cold leg side of theSG, prior to operation. In addition, the U-bend region of the small radius tubes were in-situ stress relieved prior to operation.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (Le.,
tube plugging or repair) taken in response to the inspection findings.
After review of the information provided by the licensee, the NRC staff has the following comment/observation:
- Two circumferential 00 stress-corrosion cracking indications that were located within free span dings in SG C were in-situ pressure tested. The amplitude of the dings were 2.25 volts and 14.84 volts. There was no evidence of leakage during the testing and the tubes did not burst. The eddy current signal obtained after the in-situ pressure test showed little change when compared to the eddy current signal obtained prior to the in-situ pressure test.
Based on a review of the information provided by the licensee, the NRC staff has concluded that the licensee provided the information required by their TSs. In addition, the NRC staff has also concluded that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
February 10, 2011 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.2 - STAFF EVAULATION REGARDING THE 2009 STEAM GENERATOR INSPECTION REPORT (TAC NO. ME3998)
Dear Mr. Harden:
By letter dated February 11, 2010, as supplemented by letters dated May 17, 2010, and January 14, 2011, FirstEnergy Nuclear Operating Company, (the licensee) submitted information summarizing the results of the 2009 steam generator (SG) tube inspections for the 14th refueling outage at Beaver Valley Power Station, Unit No.2 (BVPS-2), in accordance with Technical Specification (TS) 5.6.6.2.4.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and has concluded that the licensee provided the information required by their TSs and that no additional follow-up is required at this time. The NRC staff's review of the report is enclosed.
Please contact me at (301) 415-1016, if you have any questions regarding this issue.
Sincerely,
/raJ Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
As stated cc wtencl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLASLittle RidsAcrsAcnw_MailCTR LPLI-1 RtF RidsNrrPMBeaverValley RidsOGCRp RidsNrrDorlDpr RidsNrrDciCsgb RidsRgn 1MailCenter RidsNrrDorlLpll-1 AJohnson KKwaroski ADAMS A ccesslon N0.: ML110390133 *See memo d aet d J anuary 25 , 2011 OFFICE DORL/LPLI-1/PIVI DORL/LPLI-1/LA DCI/CSGB/BC DORL/LPLI-1/BC NAME I\IMorgan SUttle RTaylor NSalgado DATE 2/9/11 2/9/11 1/25/2011* 2/10/11 OFFICIAL RECORD COPY