Letter Sequence Withdrawal |
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MONTHYEARML0208403382002-03-23023 March 2002 Request for Withholding Information from Public Disclosure (Tac No. MB3902) Project stage: Withholding Request Acceptance ML0208605052002-03-27027 March 2002 NRC Staff Review of License Amendment Request Regarding the Use of the Westinghouse Master Curve Methodology (Tac No. MB3902) Project stage: Approval ML0215503982002-04-23023 April 2002 Application of Master Curve Facture Toughness for Reactor Pressure Vessel Integrity Evaluation of BVPS-1 Project stage: Request ML0215503882002-05-17017 May 2002 Master Curve Submittal, NRC Staff Observations Project stage: Other ML0215402232002-05-30030 May 2002 Summary of April 23, 2002, Meeting an Application for a License Amendment to Allow Fenoc to Use the Westinghouse Master Curve Methodology to Establish Reactor Vessel Pressure-Temperature Limits (Tac No. MB3902) Project stage: Meeting ML0226000852002-09-17017 September 2002 Withdrawal of an Amendment Request and Requests for Associated Exemptions Project stage: Withdrawal ML0227506272002-10-0303 October 2002 Return of Proprietary Materials Associated with Withdrawn Amendment Request and Requests for Associated Exemptions Project stage: Other 2002-04-23
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Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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 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-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report 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 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) 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 05000334/LER-2024-004, 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 ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, 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 05000334/LER-2024-002, 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 05000334/LER-2024-001, 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 ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - 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Text
September 17, 2002 Mr. Mark B. Bezilla Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - WITHDRAWAL OF AN AMENDMENT REQUEST AND REQUESTS FOR ASSOCIATED EXEMPTIONS (TAC NOS. MB3902 and MB3927)
Dear Mr. Bezilla:
By letter dated January 25, 2002, you applied for an amendment to the Beaver Valley Power Station, Unit No. 1 (BVPS-1), Operating License No. DPR-66. The proposed change would have modified the facility technical specifications pertaining to reactor coolant system heatup/cooldown curves, power operated relief valve setpoint and overpressure protection system enable temperature based upon use of Westinghouses Master Curve methodology.
Your January 25, 2002, letter also included associated exemption requests. Subsequently, by letter dated September 4, 2002, you withdrew the amendment request and the request for the associated exemptions.
The purpose of this letter is to advise that the above cited application is being treated as withdrawn. Notice of Consideration of Issuance of the proposed amendment had not been published in the Federal Register.
Your September 4, 2002, letter also requested that the NRC reinitiate a review of the BVPS-1 Capsule X withdrawal schedule that had been submitted on March 7, 2001, but which had been deferred because the capsule withdrawal schedule would have been superceded by the new schedule provided in your amendment request. Accordingly, NRC review of the Capsule X withdrawal schedule for BVPS-1 will be completed under TAC number MB3901 and the TAC numbers associated with the subject amendment request and exemption requests will be closed.
Sincerely,
/RA/
Daniel S. Collins, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334 cc: See next page
September 17, 2002 Mr. Mark B. Bezilla Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - WITHDRAWAL OF AN AMENDMENT REQUEST AND REQUESTS FOR ASSOCIATED EXEMPTIONS (TAC NOS. MB3902 and MB3927)
Dear Mr. Bezilla:
By letter dated January 25, 2002, you applied for an amendment to the Beaver Valley Power Station, Unit No. 1 (BVPS-1), Operating License No. DPR-66. The proposed change would have modified the facility technical specifications pertaining to reactor coolant system heatup/cooldown curves, power operated relief valve setpoint and overpressure protection system enable temperature based upon use of Westinghouses Master Curve methodology.
Your January 25, 2002, letter also included associated exemption requests. Subsequently, by letter dated September 4, 2002, you withdrew the amendment request and the request for the associated exemptions.
The purpose of this letter is to advise that the above cited application is being treated as withdrawn. Notice of Consideration of Issuance of the proposed amendment had not been published in the Federal Register.
Your September 4, 2002, letter also requested that the NRC reinitiate a review of the Capsule X withdrawal schedule that had been submitted on March 7, 2001, but which had been deferred because the capsule withdrawal schedule would have been superceded by the new schedule provided in your amendment request. Accordingly, NRC review of the Capsule X withdrawal schedule for BVPS-1 will be completed under TAC number MB3901 and the TAC numbers associated with the subject amendment request and exemption requests will be closed.
Sincerely,
/RA/
Daniel S. Collins, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334 cc: See next page DISTRIBUTION:
PUBLIC MO'Brien ACRS SRichards PDI-1 Reading DCollins OGC BPlatchek, RGN-I MMitchell RLaufer LLois ACCESSION NO. ML022600085 OFFICE PDI-1/LA PDI-1/PM PDI-1/SC NAME MOBrien DCollins RLaufer DATE 9/13/02 9/13/02 9/16/02 OFFICIAL RECORD COPY
Beaver Valley Power Station, Units 1 and 2 Mary OReilly, Attorney Division of Nuclear Safety FirstEnergy Nuclear Operating Company Bureau of Radiation Protection FirstEnergy Corporation Deparment of Environmental Protection 76 South Main Street Rachel Carson State Office Building Akron, OH 44308 P.O. Box 8469 Harrisburg, PA 17105-8469 FirstEnergy Nuclear Operating Company Regulatory Affairs/Corrective Action Section Mayor of the Borough of Larry R. Freeland, Manager Shippingport Beaver Valley Power Station P O Box 3 Post Office Box 4, BV-A Shippingport, PA 15077 Shippingport, PA 15077 Regional Administrator, Region I Commissioner James R. Lewis U.S. Nuclear Regulatory Commission West Virginia Division of Labor 475 Allendale Road 749-B, Building No. 6 King of Prussia, PA 19406 Capitol Complex Charleston, WV 25305 Resident Inspector U.S. Nuclear Regulatory Commission Director, Utilities Department Post Office Box 298 Public Utilities Commission Shippingport, PA 15077 180 East Broad Street Columbus, OH 43266-0573 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Director, Pennsylvania Emergency ATTN: M. P. Pearson, Director Management Agency Services and Projects (BV-IPAB) 2605 Interstate Dr. Post Office Box 4 Harrisburg, PA 17110-9364 Shippingport, PA 15077 Ohio EPA-DERR FirstEnergy Nuclear Operating Company ATTN: Zack A. Clayton Beaver Valley Power Station Post Office Box 1049 Mr. B. F. Sepelak Columbus, OH 43266-0149 Post Office Box 4, BV-A Shippingport, PA 15077 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 L. W. Pearce, Plant Manager (BV-IPAB)
FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 Rich Janati, Chief