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MONTHYEARML20324A2272020-11-0808 November 2020 10 CFR 2.206 Petition (Beaver Valley Power Station, Unit No. 2) Submitted by Thomas Saporito, Executive Director, Nuclear Energy Oversight Project Project stage: Other ML20323A0452020-11-17017 November 2020 2.206 Petition Project stage: Other 2020-11-17
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Category:2.206 Petition
MONTHYEARML20324A2272020-11-0808 November 2020 10 CFR 2.206 Petition (Beaver Valley Power Station, Unit No. 2) Submitted by Thomas Saporito, Executive Director, Nuclear Energy Oversight Project ML18194A3952018-06-19019 June 2018 10 CFR 2.206 Petition Review Board First Energy Nuclear Facility Operating Company in Ohio and Pennsylvania - Official Transcript of Proceedings ML17081A4182017-03-0808 March 2017 10 CFR 2.206 Petition Review Board (PRB) Conference Call Beyond Nuclear ML0511002972005-04-12012 April 2005 G20050272 - David A. Lochbaum Ltr. Re 2.206 - Enforcement Action Against Firstenergy for Beaver Valley 10 CFR 50.9 Violation 2020-11-08
[Table view] Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-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 ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20240102024-08-20020 August 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010 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 IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 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-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control 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 ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) 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-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations 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 IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 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 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report 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 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions 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 IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 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 2024-09-17
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Nuclear Energy Oversight Project Oversight of the U.S. Nuclear Regulatory Commission to protect public health and safety and the environment 9995 SE Federal Hwy. Unit 1763 Thomas Saporito Hobe Sound, Florida 33475 Executive Director Phone: (772) 206-2489 Email: saporito@gmx.com November 8, 2020 Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555 (Sent via Electronic Mail)
RE: 10 CFR 2.206 PETITION (BEAVER VALLEY POWER STATION, UNIT NO. 2)
The Nuclear Energy Oversight Project (NEOP) - by and through its undersigned Executive Director (Petitioners) - hereby submit a 10 CFR 2.206 Petition requesting that the U.S. Nuclear Regulatory Commission (NRC) take enforcement action against its licensee(s) -
Energy Harbor Nuclear Corp. - Beaver Valley Power Station, Unit No. 2 - as delineated below:
Requested Enforcement Action Petitioners request that the NRC:
DENY and refuse to accept assertions made by the licensee to the NRC by letter dated October 28, 2020 (L-20-205) - regarding the Reactor Vessel Capsule Y Analysis Report WCAP-18558-NP.
Issue a Confirmatory Order (CO) requiring the licensee to test Reactor Surveillance Capsules utilizing the Tinius-Olsen Model IT406 or Model IT542 - Pendulum Impact test machines - or equivalent machines with the same accuracy or better accuracy -
or contract the testing to an outside vendor with such testing equipment - which complies with ASTM E23, EN10045-2 and ISO 148.
Issue a CO requiring the licensee to identify the model number of the Instron Impulse system (Striker) used in concert with the Tinius-Olsen Model 74, 358J machine - to test the Reactor Vessel Capsule Y - for which the licensee obtained the data reported in WCAP-18558-NP to the NRC.
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Issue a CO requiring the licensee to identify any outside contractor that was contracted by the licensee to perform the Charpy tests on the Reactor Vessel Capsule Y from the Beaver Valley Power Station,Unit No. 2 (BVPS-2), reactor vessel.
Basis and Justification By letter dated October 28, 2020 (L-20-205) - regarding the Reactor Vessel Capsule Y Analysis Report - the licensee notified the NRC - in part relevant - that:
. . . The enclosed report WCAP-18558-NP, "Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," includes a technical summary of the results of the mechanical property tests conducted on the fifth capsule withdrawn from the Beaver Valley Power Station,Unit No. 2 (BVPS-2), reactor vessel. . .Testing was performed in accordance with ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," as specified in 10 CFR 50, Appendix H, paragraph III.B.1. . . "
(I.d. at p.1).
In the licensee's report WCAP-18558-NP - the licensee advised the NRC in relevant part that:
". . . The Charpy impact tests were performed per ASTM Specification E185-82
[8] and E-23-18 [9] on a Tinius-Olsen Model 74, 358J machine. The Charpy machine striker was instrumented with an Instron Impulse system. . ."
(Id. at p.5-1).
Petitioners aver here that the NRC cannot accept or rely on the data provided by the licensee regarding the Reactor Vessel Capsule Y Analysis Report (WCAP-18558-NP) -
because the licensee failed to identify the Model Number of the Instron Impulse system which the Charpy machine striker was instrumented with.
Petitioners further aver here that the NRC cannot accept or rely on the data provided by the licensee regarding the Reactor Vessel Capsule Y Analysis Report (WCAP-18558-NP) -
because the licensee obtained data on the Beaver Valley Power Station,Unit No. 2 (BVPS-2),
reactor vessel Capsule Y - using an outdated Charpy test machine. Notably - the Tinius-Olsen Model 74, 358J machine relied upon by the licensee - as modified with the Instron Impulse system - is apparently no longer manufactured - and has been replaced with more accurate Charpy test machines - which do not involve interpretation of an analog gauge by a human.
The current Tinius-Olsen pendulum impact testers are versatile and reliable machines designed to fully comply with the specifications outlined in ASTM E23, EN10045-2 and ISO 148. Notably - the Model IT406 and the Model IT542 are widely recognized as the standards of the industry for impact testing - which offer options such as an automatic motorized return -
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eliminating the need for an operator involvement other than releasing the pendulum.
Moreover - machines with a digital display can be linked to a stand alone PC and connected to Tinius Olsen's Horizon software.
Petitioners note here that digital displays are far more accurate that human interpretations of analog displays.
For the Petitioners Thomas Saporito Executive Director
- A copy of this document will be provided to the NRC Office of the Inspector General (OIG) to enable that agency to monitor NRC's actions in this matter accordingly.
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