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Category:Letter type:L
MONTHYEARL-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024
30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative
L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024
License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
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-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023
CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023
Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20
L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023
Submittal of the Updated Safety Analysis Report, Revision 23
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-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
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-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023
Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD
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-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023
License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023
30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative
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-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023
License Renewal Application for the Perry Nuclear Power Plant
L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023
Plan, Nineteenth Inservice Inspection Summary Report
L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
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-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023
License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
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
L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
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-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
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-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
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-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023
Annual Radiological Effluent Release Report
L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023
Annual Radiological Environmental Operating Report
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-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023
Core Operating Limits Report for Operating Cycle 20
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023
180-Day Steam Generator Tube Inspection Report
2024-01-24
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FENOC ft*-O 76 South Main Street FirstEnergyNuclear OperatingCompany Akron, Ohio 44308 Danny L. Pace 330-384-3733 Senior Vice President.Engineering Fax: 330-384-3799 June 8, 2006 BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L U. S. Nuclear Regulatory Commission Attention: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Beaver Valley Power Station, Unit Nos. 1 and 2 Docket Nos. 50-334 and 50-412 Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346 Perry Nuclear Power Plant, Unit 1 Docket No. 50-440
Subject:
Response to NRC Generic Letter 2006-03 On April 10, 2006, the NRC issued Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations." The NRC issued the letter to request that addressees evaluate their facilities to confirm compliance with the existing applicable regulatory requirements in light of the information provided in this Generic Letter and, if appropriate, take additional actions.
The FirstEnergy Nuclear Operating Company (FENOC) is submitting the attached response (Attachment 1) to address the Generic Letter for the Beaver Valley Power Station, Unit Nos. 1 and 2, the Davis-Besse Nuclear Power Station, Unit 1, and the Perry Nuclear Power Plant, Unit 1.
BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L Page 2 of 2 There are no commitments included in this response (Attachment 2). If there are any questions or additional information is required, please contact Mr. Gregory A. Dunn, Manager- Fleet Licensing, at (330) 315-7243.
I declare under the penalty of perjury that the foregoing is true and correct. Executed on June 8, 2006.
Very truly yours, Danny L. Pace Senior Vice President, Fleet Engineering Attachments (2)
- 1. Response to Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations"
- 2. Regulatory Commitments cc: NRC Project Manager - Beaver Valley Power Station NRC Project Manager - Davis-Besse Nuclear Power Station NRC Project Manager- Perry Nuclear Power Plant NRC Resident Inspector - Beaver Valley Power Station NRC Resident Inspector - Davis-Besse Nuclear Power Station NRC Resident Inspector - Perry Nuclear Power Plant NRC Regional Administrator - Region I NRC Regional Administrator - Region III
Attachment 1 BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L Page 1 of 3 Response to Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations" NRC Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations," requests that licensees evaluate their facilities to confirm compliance with the existing applicable regulatory requirements in light of the information provided in this Generic Letter and, if appropriate, take additional actions.
Each Generic Letter question is listed below, in bold, followed by the FENOC response.
- 1. Within 60 days of the date of this GL, provide the following:
- a. A statement on whether Hemyc or MT fire barrier material is used at their NPPs and whether it is relied upon for separation and/or safe shutdown purposes in accordance with the licensing basis, including whether Hemyc or MT is credited in other analyses (e.g.,
exemptions, license amendments, GL 86-10 analyses).
Neither Hemyc nor MT fire barrier material is currently being used at the Beaver Valley Power Station (Beaver Valley), Unit Nos. 1 and 2, the Davis-Besse Nuclear Power Station (Davis-Besse), Unit 1, or the Perry Nuclear Power Plant (Perry), Unit 1.
- b. A description of the controls that were used to ensure that other fire barrier types relied on for separation of redundant trains located in a single fire area are capable of providing the necessary level of protection. Addressees may reference their responses to GL 92-08 to the extent that the responses address this specific issue.
The fire barrier types that are relied on for the separation of redundant trains in a single fire area have been tested or evaluated to determine that they are capable of providing the necessary level of protection. In response to Generic Letter 92-08, actions were taken at Beaver Valley, Davis-Besse, and Perry to address this issue and responses were provided to the NRC. Additional information can be found in the docketed responses to Generic Letter 92-08.
At Beaver Valley, Thermo-Lag, 3M Interam E50 Series, and Darmatt KM-1 fire barrier material is used for separation of redundant trains located in a single fire area. This material was evaluated as requested in Generic
Attachment 1 BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L Page 2 of 3 Letter 92-08 and NRC Information Notice 93-41, "One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-1 95 and 3M Company Interam E-50 Fire Barrier Systems," and found to be in compliance with the NRC requirements. Tests and evaluations were performed for Beaver Valley to determine that the Thermo-lag material properties and attributes conform to NRC regulations. Tests and evaluations were also performed on the 3M Interam E50 Series, and Darmatt KM-1 fire barrier material to determine that they conform to NRC regulations.
At Davis-Besse and Perry, 3M Interam E50 Series Flexible Mat is credited as the fire barrier material that is used to protect circuits. The 3M Interam material was installed as a replacement for Thermo-Lag in response to Generic Letter 92-08 and was qualified using test data to evaluate the fire barrier installations for endurance, combustibility, and acceptable ampacity derating factors. Some Thermo-Lag applications were retained, but are no longer credited as fire barrier material that is used to protect circuits.
Based on the tests and evaluations summarized above, Beaver Valley, Davis-Besse, and Perry each concluded that the existing fire barrier materials are capable of providing the necessary level of protection.
- 2. Within 60 days of the date of this GL, for those addressees that have installed Hemyc or MT fire barrier materials, discuss the following in detail:
- a. The extent of the installation (e.g., linear feet of wrap, areas installed, systems protected),
Not applicable - neither Hemyc nor MT fire barrier material is currently being used at Beaver Valley, Davis-Besse, or Perry.
- b. Whether the Hemyc and/or MT installed in their plants is conforming with their licensing basis in light of recent findings, and if these recent findings do not apply, why not, Not applicable - neither Hemyc nor MT fire barrier material is currently being used at Beaver Valley, Davis-Besse, or Perry.
Attachment 1 BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L Page 3 of 3
- c. The compensatory measures that have been implemented to provide protection and maintain the safe shutdown function of affected areas of the plant in light of the recent findings associated with Hemyc and MT installations, including evaluations to support the addressees' conclusions, and Not applicable - neither Hemyc nor MT fire barrier material is currently being used at Beaver Valley, Davis-Besse, or Perry.
- d. A description of, and implementation schedules for, corrective actions, including a description of any licensing actions or exemption requests needed to support changes to the plant licensing basis.
Not applicable - neither Hemyc nor MT fire barrier material is currently being used at Beaver Valley, Davis-Besse, or Perry.
- 3. No later than December 1, 2007, addressees that identified in l.a.
Hemyc and/or MT configurations are requested to provide a description of actions taken to resolve the nonconforming conditions described in 2.d.
Not applicable - neither Hemyc nor MT fire barrier material is currently being used at Beaver Valley, Davis-Besse, or Perry.
Attachment 2 BV-L-06-086 DB-Serial Number 3268 PY-CEI/NRR-2967L Page 1 of 1 Regulatory Commitments The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for the Beaver Valley Power Station, Unit Nos. I and 2, the Davis-Besse Nuclear Power Station, Unit 1, and the Perry Nuclear Power Plant, Unit 1. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not regulatory commitments. Please notify Mr. Gregory A. Dunn, Manager - Fleet Licensing at (330) 315-7243 of any questions regarding this document or associated regulatory commitments.
Commitment Due Date None N/A