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MONTHYEARL-14-064, Supplemental Information Regarding Application for License Amendment to Adopt NFPA 805, Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2014-02-14014 February 2014 Supplemental Information Regarding Application for License Amendment to Adopt NFPA 805, Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Supplement ML14108A4082014-04-22022 April 2014 Acceptance of Requested Licensing Action License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Generating Plants Project stage: Acceptance Review ML14122A1062014-05-12012 May 2014 National Fire Protection Association Standard 805 License Amendment Application Online Reference Portal Project stage: Other L-14-181, Online Reference Portal for Review of National Fire Protection Association Standard 805 License Amendment Application2014-06-25025 June 2014 Online Reference Portal for Review of National Fire Protection Association Standard 805 License Amendment Application Project stage: Other ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) Project stage: Other L-15-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-04-27027 April 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) Project stage: RAI L-15-188, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-06-26026 June 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI ML15203A1882015-07-28028 July 2015 February 23-26, 2015, Summary of Beaver Valley Audit Associated with License Amendment Request to Transition to National Fire Protection Association 805 Standards Project stage: Other 2015-01-28
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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] Category:Schedule and Calendars
MONTHYEARML15203A1882015-07-28028 July 2015 February 23-26, 2015, Summary of Beaver Valley Audit Associated with License Amendment Request to Transition to National Fire Protection Association 805 Standards L-11-214, Response to NRC Regulatory Issue Summary 2011-04 Preparation and Scheduling of Operator Licensing Examinations2011-07-0505 July 2011 Response to NRC Regulatory Issue Summary 2011-04 Preparation and Scheduling of Operator Licensing Examinations ML0926105222009-09-28028 September 2009 Revision of Schedule for the Conduct of Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC MD6593, MD6594, MD6595, MD6596) ML0813605572008-05-22022 May 2008 Revision of Schedule for the Conduct of Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application L-06-140, Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations2006-09-13013 September 2006 Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations 2015-07-28
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Text
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.L UNITED STATES IJ)
- 0 NUCLEAR REGULATORY COMMISSION
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l WASHINGTON, D.C. 20555-0001 I') ~o Jul y 28, 2015
Mr. Eric A. Larson, 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 NOS. 1AND2,
SUMMARY
OF AUDIT OF FEBRUARY 23-26, 2015, ASSOCIATED WITH LICENSE AMENDMENT REQUEST TO TRANSITION TO NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. MF3301 AND MF3302)
Dear Mr. Larson:
A review team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff, and contractors from the Pacific Northwest National Laboratory (PNNL) and Southwest Research Institute/Center for Nuclear Waste Regulatory Analyses (CNWRA), conducted a regulatory audit at the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) in Shippingport, Pennsylvania on February 23 - 26, 2015. This audit was associated with the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, license amendment request (LAR) dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML14002A086), as supplemented.
The regulatory audit supports the review of the LAR filed by First Energy Nuclear Operating Company to transition the plant's fire protection licensing basis to Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.48(c), which endorses, with exceptions, NFPA 805, 2001 Edition.
The purpose of the audit was to gain an understanding of the information needed to support the NRC staff's licensing decision regarding the LAR and to develop high quality requests for additional information (RAI}, as needed. The information submitted in support of the BVPS-1 and 2 LAR is under final review. Any additional information needed to support the LAR review will be formally requested by the staff using the RAI process in accordance with Office of Nuclear Reactor Regulation Office Instruction LIC-101 , "License Amendment Review Procedures."
The audit team consisted of twelve NRC staff from NRC headquarters located in Rockville, Maryland, four NRC staff from NRC Region 1, two NRC contractors from PNNL, and two NRC contractors from CNWRA. Enclosure 1 provides the schedule of activities during the audit.
Enclosure 2 lists audit team participants from NRC, PNNL, CNWRA, BVPS, and the licensee's contractors who participated in the audit.
The NRC audit team held an entrance meeting on February 23, 2015, with the licensee's staff and contractors. During the remainder of the audit, team members participated in technical discussions based on their discipline according to the audit plan available in ADAMS under Accession No. ML15027A235. Technical discussions were focused on five major areas: fire
E. Larson protection engineering , safe shutdown/circuit analyses, fire probabilistic risk assessment, fire modeling, and programmatic* review. The audit team participated in plant walkdowns , tours, and technical presentations focusing on these topical areas.
At the conclusion of the audit, the audit team participated in a summary exit meeting with the licensee on February 26, 2015. The NRC staff provided a brief conclusion of the team goals, objectives, walkdown experience , and technical discussions.
Please direct any inquiries to me at (301) 415-7128 orTaylor.Lamb@nrc.gov.
Sine~ CJ!/a4 Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosures:
- 1. Schedule of Activities
- 2. List of Participants
- 3. List of Documents Reviewed cc w/
Enclosures:
Distribution via Listserv
ML15203A188 *via memo OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPLI 1-2/LA N RR/ORA/AF PB/BC NAME TLamb LRonewicz AKlein*
DATE 7/27/15 7/28/15 6/9/15 OFFICE NRR/DRA/APRA/BC NRR/DORL/LPL 1-2/BC NRR/DORL/LPL 1-2/PM NAME SRosenberg* DBroaddus (REnnis for) TLamb DATE 6/9/15 7/27/15 7/28/15 Schedule of Activities Monday. February 23, 2015 8:00 am Audit team .members met onsite at the Beaver Valley Power Station 9:00 am Audit entrance meeting and virtual tour were conducted 10:00 am Commence technical discussions for fire probabilistic risk assessment (PRA),
fire modeling (FM) , and safe shutdown (SSD)/fire protection engineering (FPE). Breakout sessions started.
12:30 pm Dosimetry badges were distributed 1:15 pm Continue technical discussions for fire PRA and FM in support of fire PRA and SSD/FPE 4:00 pm Technical discussion on incipient detection plant modification 4:55 pm U.S. Nuclear Regulatory Commission (NRC) debrief meeting 5:00 pm Licensee wrap-up meeting Tuesday. February 24, 2015 8:00 am Briefings and preparations for plant walkdowns completed . Walkdowns conducted in predetermined areas according in accordance with walkdown plan. Groups were broken into SSD, PRA, and FM disciplines.
1:15 pm Continue technical reviews for fire PRA, FM , and SSD 4:00 pm Presentation on plant Attachment S and presentation of plant modifications 4:30 pm
- NRC debrief meeting 5:00 pm Licensee wrap-up meeting Wednesday. February 25, 2015 8:00 am Continued technical reviews for fire PRA and FM in support of fire PRA and SSD 1:00 pm Request for additional information timeline discussion 2:00 pm Combined SSD/PRA meeting 2:30 pm Radiation release discussion 3:00 pm Additional modification discussion with licensee 4:30 pm NRC debrief meeting 4:45 pm Licensee wrap-up 5:00 pm Simulator tour conducted Thursday, February 26, 2015 8:15 am Additional modification discussion with licensee 9:00 am Closeout meeting for FPE/SSD 9:30 am Closeout meeting for Fire Modeling 12:00 pm Exit meeting Enclosure 1
List of Participants U.S. Nuclear Regulatory Commission (NRC) Team
- Alex Klein NRC Branch Chief
- Hossein Hamzehee NRC Branch Chief
- Stephanie Galbreath NRC Region I Observer
- John Richmond NRC Region I Observer
- Keith Young NRC Region I Observer Pacific Northwest National Lab (PNNL) Team
- Fleur de Peralta PNNL FPE
- Garill Coles PNNL FPRA Center for Nuclear Waste Regulatory Analyses (CNWRA) Team
- Nathan Hall CNWRA Programmatic Beaver Valley Power Station Team
- Eric Larson FE NOC Site Vice President
- Chaz McFeaters FE NOC Director, Site Operation
- Tim Steed FE NOC Director, Performance Improvement
- Dave Huff FE NOC Director, Maintenance
- Mark Manoleras FE NOC Director, Engineering
- Will Cothen FE NOC Manager, Compliance
- Carmen Mancuso FE NOC Manager, Design Engineering
- Thomas Migdal FE NOC Operations Enclosure 2
- Samantha Milosh FE NOC Operations
. Dave Held FENOC . Operations
- Jeff Miller FE NOC Fire Marshall
. Derek Gmys FE NOC Fire System Engineer
. Brian Sepelak FE NOC Supervisor, Regulatory Compliance
- Dave McCreary FE NOC Licensing
List of Documents Reviewed
- Letter from J.J. Carey of Duquesne Light Company (DLC) to Steven A. Varga of the U.S. Nuclear Regulatory Commission (NRC), Re : Beaver Valley Power Station, Supplemental Information to Fire Protection -Appendix R Review Report, dated October 22, 1982
- Letter from J.J. Carey of DLC to Steven A. Varga of the NRC,
Reference:
Fire Protection - Response to Appendix R Requirements and Generic Letter 81-12 , dated June 30, 1982, and enclosures related to Chapters 6, 8, 9, 11
- Letter from Steven A. Varga of NRC to J.J. Carey of DLC,
Subject:
Request for Exemption from Some Requirements of Appendix R to 10 CFR 50, dated March 14, 1983
- Letter from Steven A. Varga of NRC to J.J. Carey of DLC,
Subject:
Request for Additional Information from Some Requirements of 10 CFR Part 50, dated August 30, 1984
- Letter from J.J. Carey of DLC to Steven A. Varga of the NRC , Reference : Appendix R -
Additional Exemption Requests Based on Generic Letter 83-33
- Document 8700-01 -062-0012, Fire PRA Task 11 Detailed Fire Modeling of 1-CV-3
- Document PRA-BV1-AL-R052, Level 2 LERF Analysis Notebook, Rev. 5a
- Report #2601 .620-000-001 : Detailed Fire Modeling Procedure
- Report #2701.620-000-004: V&V of Fire Modeling Tools
- Report #2701.620-000-020 : Unit 2 MCR Detailed Fire Modeling
- Report #2701.620-000-022 : Multi-Compartment Fire Analysis
- Report #2701 .620-000-026: Detailed Fire Modeling Report for 2-CB-1
- Report #2701.620-000-027 : Detailed Fire Modeling Report for 2-CB-6
- Report #2701 .620-000-028: Detailed Fire Modeling Report for 2-CV-1
- Report #2701 .620-000-039: Detailed Fire Modeling Report for 2-SB-2
- Report #2701 .620-000-040: Detailed Fire Modeling Report for 2-SB-3
- Report #2701 .620-000-050: Fire Modeling V&V
- Report #8700- 01.062~0017 : Detailed Fire Modeling Report for 1-CR-4 Enclosure 3
- Report #8700-01 .062-0023: Detailed Fire Modeling Report for 1-ES-1
- Report #8700-01 .062-0024: Detailed Fire Modeling Report for 1-ES-2
- Report #8700-01 .062:-0027: Detailed Fire Modeling Report for 1-NS-1
- Report #8700-01 .062-0034: Unit 1 MCR Detailed Fire Modeling