Similar Documents at Perry |
|---|
Category:Letter type:L
MONTHYEARL-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-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-23-171, 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-23-244, 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-23-238, 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-23-206, 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-23-205, 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-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
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-23-188, 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-23-174, 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-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023
License Renewal Application for the Perry Nuclear Power Plant
L-23-051, 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-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-23-134, 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-23-121, 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-23-061, 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-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-085, 1 to Emergency Plan2023-03-10010 March 2023
1 to Emergency Plan
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-23-017, Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 192023-01-31031 January 2023
Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 19
L-22-271, Emergency Plan2022-12-20020 December 2022
Emergency Plan
L-22-272, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)2022-12-16016 December 2022
Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)
L-22-263, Spent Fuel Storage Cask Registration2022-12-12012 December 2022
Spent Fuel Storage Cask Registration
L-22-254, Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 222022-11-18018 November 2022
Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 22
L-22-250, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 192022-11-0808 November 2022
Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 19
L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-10-18018 October 2022
Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
L-22-201, Submittal of Evacuation Time Estimates2022-09-12012 September 2022
Submittal of Evacuation Time Estimates
L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022
Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022
Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
L-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-0632022-07-14014 July 2022
Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063
L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022
Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis
L-22-104, Annual Radiological Environmental Operating Report2022-04-28028 April 2022
Annual Radiological Environmental Operating Report
L-22-110, Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement2022-04-28028 April 2022
Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement
L-22-105, Annual Radiological Effluent Release Report2022-04-27027 April 2022
Annual Radiological Effluent Release Report
L-22-082, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-23023 March 2022
Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022
Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage
L-22-052, Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines2022-03-16016 March 2022
Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines
L-22-073, Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant2022-03-16016 March 2022
Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant
L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022
Retrospective Premium Guarantee
L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements2022-01-0505 January 2022
10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements
L-21-282, Proposed Inservice Inspection Alternative IR-0632022-01-0505 January 2022
Proposed Inservice Inspection Alternative IR-063
L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing2021-12-28028 December 2021
10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing
L-21-287, Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)2021-12-20020 December 2021
Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)
2024-01-24
[Table view] |
Text
, Perry Nuclear Power Plant 10 Center Road Perry, Ohio 44081 RrstEnergy Nuclear Operating Company Vito A. Ksminskas 440-280-5382 Vice President Fax: 440-280-8029 November 14, 2012 L-12-312 A TIN: Document Control Desk U.S. Nuclear Regulatory Commission*
Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Notification of the Intended Use of Lead Test Assemblies In accordance with NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR II)," the FirstEnergy Nuclear Operating Company (FENOC) is making a notification to the Nuclear Regulatory Commission (NRC) of the intended use of lead test assemblies (LTA) at the Perry Nuclear Power Plant (PNPP).
A letter dated September 23,1981 from the NRC to the General Electric Company, referenced in GESTAR II, indicates the notification should include a description of the LTAs, a statement of applicability to GESTAR II, the objectives of the LTA program, and an outline of the measurements to be made on the LTAs. The attachment provides this information.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.
Sincerely, t/d-f2
. Vito A. Kaminskas
Attachment:
Lead Test Assemblies for Use in Perry Nuclear Power Plant Fuel Cycle 15 cc: NRC Region III Administrator NRC Project Manager NRC Resident Inspector
Attachment l-12-312 lead Test Assemblies for Use in Perry Nuclear Power Plant Fuel Cycle 15*
Page 1 of 2 Description of Lead Test Assemblies Two lead test assemblies (lTAs) , originally loaded into the Perry Nuclear Power Plant (PNPP) core prior to the start of operating cycle 11, which began in May 2005, and discharged after operating cycle 13, which ended in April 2011, will be reinserted prior to the start of operating cycle 15, which begins in spring 2013. The Global Nuclear Fuel- Americas, llC (GNF) supplied assemblies contain standard GE14 components and fuel, with the exception of the channel. The channels were manufactured with a distortion-resistant material known as NSF. The term NSF reflects the presence of niobium, tin, and iron as the primary alloying metals combined with zirconium. Similar niobium-containing zirconium alloys are commonly used in pressurized water reactors and Russian plants, but not commercially used in boiling water reactors.
The NSF alloy is resistant to channel bowing and has a much lower sensitivity to cold-work compared to Zircaloy. The mechanical properties of NSF are similar to the standard Zircaloys and are considered adequate for reactor service. Corrosion performance of NSF is adequate based on visual examination after six years of operation.
These two l TAs are in addition to eight l TAs that were inserted into the PNPP core prior to the start of operating cycle 14, which began in June 2011. FENOC provided notification for these eight l TAs by letter dated April 15, 2011 (AcceSSion No.
Ml111050424).
Applicability of NEDE-24011-P-A. uGeneral Electric Standard Application for Reactor Fuel (GESTAR 11)"
GNF has reviewed the properties of the NSF channels relative to the properties of Zircaloy-2 and Zircaloy-4 in the context of required functions, including safety. This review included GESTAR II and license topical reports: NEDE-21354-P, "BWR Fuel Channel Mechanical Design and Deflection," September 1976, and NEDE-21175 P-A, "BWR Fuel Assembly Evaluation of Combined Safe Shutdown Earthquake (SSE) and loss-of-Coolant Accident (lOCA) loadings," Amendment 3, October 1984. GNF has concluded that the use of NSF as a channel material meets the approved criteria of GESTAR II and may be used in an l TA.
Attachment L-12-312 Page 2 of2 Objectives of LTA Program The objectives of this program are to expand the experience base on NSF channels and to characterize the corrosion performance out to the limiting residence time.
Channel distortion will be monitored to confirm the observations already made regarding resistance to channel bow. Standard analyses will be performed to assure that the safety and licensing bases are maintained.
Outline of Measurements Corrosion performance will be evaluated visually and potentially with a non-destructive system to measure oxide thickness. Distortion measurements will be made after discharge. Depending on the observed performance and the potential for long-term application, coupons (material samples from irradiated channels) may be extracted for hotcell examination.
