Letter Sequence Approval |
---|
|
|
MONTHYEARML0316814262003-08-12012 August 2003 Issuance of Amendment No. 255, Revisings TS 3/4.4.4 to Adopt a New Pressurizer High Level Limit Based on Providing Enough Steam Volume to Prevent a Pressurizer High Level Project stage: Approval 2003-08-12
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 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 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan 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 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) 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 IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 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 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) 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 IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23160A2342023-06-13013 June 2023 Confirmation of Initial License Examination 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 IR 05000346/20235012023-06-13013 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501 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-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report 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 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) ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information 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 IR 05000346/20230102023-05-0909 May 2023 Commercial Grade Dedication Inspection Report 05000346/2023010 ML23123A1272023-05-0303 May 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station IR 05000346/20230012023-05-0101 May 2023 Integrated Inspection Report 05000346/2023001 and 07200014/2022001 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 ML23111A1972023-04-26026 April 2023 Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station ML23114A1062023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23096A1382023-04-11011 April 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports 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 ML23066A2892023-03-14014 March 2023 Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement ML23066A2592023-03-14014 March 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 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23237B4412023-09-29029 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Federal Register Notice, Direct and Indirect License Transfer Issuance Order ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML22269A3582022-11-15015 November 2022 Issuance of Amendment No. 305 Revising the Emergency Plan ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML20030A4402020-02-27027 February 2020 Issuance of Amendment Nos. 304, 194, 299, and 187; Order Approving Transfers of Facility Operating Licenses and Independent Spent Fuel Storage Installation General Licenses and Conforming Amendments ML19326A7592019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Non-Proprietary, Letter & Encl 2-5, Order Approving Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML17270A1122017-10-19019 October 2017 Issuance of Amendment Revising Technical Specification Requirements for Ultrasonic Flow Meter Outage Time (CAC No. MF9080; EPID L-2017-LLA-0167) ML17219A0182017-08-0808 August 2017 License Renewal Commitment No. 42 ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme ML16298A3492017-01-11011 January 2017 Issuance of Amendment Revising Technical Specification Requirements for the Radioactive Effluent Controls Program ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML16083A4812016-04-27027 April 2016 Issuance of Amendment Revising Emergency Diesel Generator Minimum Voltage and Frequency Acceptance Criteria ML15302A0752016-03-0808 March 2016 Issuance of Amendment Revising the Completion Date for Milestone 8 of the Cyber Security Plan ML15316A0562015-12-0808 December 2015 Renewal License ML15295A3192015-12-0707 December 2015 License Renewal Application for Davis-Besse Nuclear Power Station, Unit 1 - Record of Decision ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement ML15239B2932015-10-0909 October 2015 Issuance of Amendment Related to Containment Leakage Rate Testing Program L-15-186, Supplemental Information for the Review Reactor Vessel Internals Inspection Plan and License Renewal Application Amendment No. 572015-06-0505 June 2015 Supplemental Information for the Review Reactor Vessel Internals Inspection Plan and License Renewal Application Amendment No. 57 ML14205A6192014-08-29029 August 2014 Amendments to Indemnity Agreements (TAC MF0701, MF0702, MF0703, and MF0704) ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC ML1208604472012-04-18018 April 2012 Issuance of Amendment Modification of the Special Visual Inspection Requirement of TS 5.5.8 Steam Generator Program ML1202502702011-12-27027 December 2011 2011 Davis - Besse Nuclear Power Station Initial Examination Administrative Files ML1125904312011-12-0909 December 2011 Issuance of Amendment Adoption of Technical Specifications Task Force Change Traveler 513, Revision to Technical Specification 3.4.14 L-11-289, License Renewal Application Amendment No. 16, Supplemental Information for the Review of the License Renewal Application Environmental Report2011-09-19019 September 2011 License Renewal Application Amendment No. 16, Supplemental Information for the Review of the License Renewal Application Environmental Report ML1118902982011-08-31031 August 2011 Issuance of Amendment Cyber Security Plan ML1036101482011-01-28028 January 2011 Issuance of Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of the Reactor Coolant System Pressure-Temperature Curves ML1009705492010-04-0909 April 2010 Corrections of Typographical Errors Amendment No. 281 and Safety Evaluation ML1006405062010-03-24024 March 2010 Issuance of Amendment Application to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds ML1003506402010-02-0404 February 2010 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License ML0918103972009-07-16016 July 2009 Issuance of Amendments Application for TS Change for Adoption of TSTF-511 ML0829006002008-11-20020 November 2008 Issuance of Amendment 279 for the Conversion to the Improved TSs with Beyond Scope Issues ML0824902622008-10-0202 October 2008 Draft Safety Evaluation for Conversion to ITS with Beyond Scope Issues, (TAC MD ML0814106522008-06-30030 June 2008 Issuance of Amendment 278 Regarding Measurement Uncertainty Recapture Power Uprate ML0723902602007-10-17017 October 2007 License Amendment, Issuance of Amendment Administrative Control of Penetrations During Refueling ML0720404172007-07-31031 July 2007 License Amendment, Issuance of Amendment Steam Generator Tube Integrity TS Amendment Using the Consolidated Line Item Improvement Process ML0719200042007-07-11011 July 2007 Revised Pages of Facility Operating License No. NPF-3 ML0604004722006-08-0909 August 2006 License Amendment, Issuance of Amendment Safety Features Actuation System Instrumentation Setpoints and Surveillance Testing Requirements, MC3084 ML0604005522006-03-0202 March 2006 License Amendment 274 Framatome Mark B-HTP Fuel Design for Cycle 15 ML0604102252006-03-0202 March 2006 Amendment License Application to Revise TS 3/4.8.1.1 A.C.Sources-Operating ML0526403932006-02-0707 February 2006 Licensing Amendment - Issuance of Amendment Administrative Controls ML0533305612006-01-31031 January 2006 Amendment, Revises Technical Specification 3/4/10.2, Special Test Exceptions - Physics Tests, to Increase Allowed Time Between Flux Channel Channel Functional Tests & Beginning of Mode 2 Physics Tests from 12 to 24 Hours ML0535402942005-12-16016 December 2005 Issuance of Conforming Amendments for Bv, Units 1 and 2; Perry, Unit 1 and Davis-Besse, Unit 1 Transfer of Ownership Interests to Fengenco - License Pages for 50-346 2023-09-29
[Table view] Category:Safety Evaluation
MONTHYEARML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML22269A3582022-11-15015 November 2022 Issuance of Amendment No. 305 Revising the Emergency Plan ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22147A1492022-06-0202 June 2022 Relief Request RP-3 Regarding Fuel Oil Transfer Pump Testing ML22136A1092022-05-24024 May 2022 Proposed Alternative Request RP-2 Regarding the Inservice Testing of Certain Pumps ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22096A3162022-04-12012 April 2022 Proposed Alternative Request RP-1 Regarding Digital Instrumentation for Inservice Testing ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17270A1122017-10-19019 October 2017 Issuance of Amendment Revising Technical Specification Requirements for Ultrasonic Flow Meter Outage Time (CAC No. MF9080; EPID L-2017-LLA-0167) ML17256B1902017-10-12012 October 2017 Time-Limited Aging Analysis for the Reactor Vessel Internals Loss of Ductility at 60 Years ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML17017A3402017-01-31031 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-051 and EA-12-049 ML16328A1252017-01-23023 January 2017 Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783) ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme ML16298A3492017-01-11011 January 2017 Issuance of Amendment Revising Technical Specification Requirements for the Radioactive Effluent Controls Program ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML16083A4812016-04-27027 April 2016 Issuance of Amendment Revising Emergency Diesel Generator Minimum Voltage and Frequency Acceptance Criteria ML15302A0752016-03-0808 March 2016 Issuance of Amendment Revising the Completion Date for Milestone 8 of the Cyber Security Plan ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement ML15211A1612015-10-16016 October 2015 FENOC-Beaver Valley Power Station, Unit No. 1; Beaver Valley Power Station ISFSI, Davis-Besse Nuclear Power Station ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI Annual Financial Test for a Parent Company Guarantee ML15239B2932015-10-0909 October 2015 Issuance of Amendment Related to Containment Leakage Rate Testing Program ML15182A1912015-07-16016 July 2015 Annual Financial Test for a Parent Company Guarantee Given by Firstenergy Solutions Corporation and Firstenergy Corporation ML14142A2922014-09-12012 September 2014 BVPS, Unit No. 1, BVPS (ISFSI) Davis-Besse Nuclear Power Station ISFSI, Perry Nuclear Power Plant, Unit 1, and Perry Nuclear Power Plant ISFSI - Annual Financial Test for Firstenergy Nuclear Operating Company Parent Company Guarantee (MF374 ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) ML14030A5742014-03-31031 March 2014 Safety Evaluation Concerning Comprehensive Pump Testing Relief Request (TAC No. MF0756) (L-13-067) ML14030A5922014-02-10010 February 2014 Safety Evaluation for Relief Requests RR-A1 and RR-B1 ML14002A4442014-02-0505 February 2014 Safety Evaluation for Relief Request RP-3 (TAC No. MF0757)(L-13-076) ML14003A2662014-01-27027 January 2014 Davis-besse Nuclear Power Station, Unit 1, Safety Evaluation for Relief Requests RP-1 and RP-1A ML13210A4672013-08-0101 August 2013 Safety Evaluation for Relief Requests RP-6 and RV-1 ML13121A4042013-05-0808 May 2013 Safety Evaluation in Support of Proposed Alternative Regarding Post-Repair Pressure Testing Requirements ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC ML12242A4992012-09-11011 September 2012 Safety Evaluation in Support of 10 CFR 50.55a Requests RP-2 and RP-4 Regarding Inservice Pump Testing ML1210706862012-05-11011 May 2012 Safety Evaluation Regarding the Reactor Coolant System Pressure and Temperature Limits Report, Revision 1 ML1208604472012-04-18018 April 2012 Issuance of Amendment Modification of the Special Visual Inspection Requirement of TS 5.5.8 Steam Generator Program ML1207504812012-04-0909 April 2012 Safety Evaluation in Support of 10 CFR 50.55a Request RR-A35, Proposed Alternative to System Leakage Test Requirements ML1124305562011-09-22022 September 2011 Request for Threshold Determination Under 10 CFR 50.80 - Beaver Valley Power Station, Unit Nos. 1 and 2; Davis-Besse Nuclear Power Station, Unit No. 1; and Perry Nuclear Power Plant, Unit No. 1 ML1118903222011-07-11011 July 2011 Review of the Steam Generator Tube Inspections Performed During Refueling Outage No. 16 in 2010 2024-01-17
[Table view] |
Text
August 12, 2003 Mr. Lew W. Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT (TAC NO. MB3749)
Dear Mr. Myers:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 255 to Facility Operating Licence NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1. This amendment revises the Technical Specifications (TS) in response to your application dated November 30, 2001.
This amendment revises TS 3/4.4.4, Reactor Coolant System - Pressurizer, to adopt a new pressurizer high level limit based on providing enough steam volume to prevent a pressurizer high level as a result of any transient. The proposed request changes the high level limit from the current 305 inches to a reduced high level limit of 228 inches. Additionally, the proposed changes would revise the TS Limiting Condition for Operation 3.4.4 Action statement to allow up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the pressurizer to operable status prior to taking action to place the plant in the Hot Standby operational mode.
A copy of the Safety Evaluation is enclosed. The notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA by JHopkins for /
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. Amendment No. 255 to License No. NPF3
- 2. Safety Evaluation cc w/encls: See next page
ML031681426 *No major changes to SE inputs.
- see previous concurrence OFFICE PDIII-2/PM PDIII-2/LA RORP/SC
- SRXB/SC OGC PDIII-2/SC NAME JHopkins for SSands PCoates for THarris KKavanagh for SMagruder** JUhle** SCole** AMendiola DATE 07/03/03 07/29/03 07/10/03 07/16/03 07/22/03 07/31/03 Davis-Besse Nuclear Power Station, Unit 1 cc:
Mary E. OReilly FirstEnergy Corporation 76 South Main St.
Akron, OH 44308 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency Manager - Regulatory Affairs 2855 West Dublin Granville Road FirstEnergy Nuclear Operating Company Columbus, OH 43235-2206 Davis-Besse Nuclear Power Station 5501 North State - Route 2 Zack A. Clayton Oak Harbor, OH 43449-9760 DERR Ohio Environmental Protection Agency Director, Ohio Department of Commerce P.O. Box 1049 Division of Industrial Compliance Columbus, OH 43266-0149 Bureau of Operations & Maintenance 6606 Tussing Road State of Ohio P.O. Box 4009 Public Utilities Commission Reynoldsburg, OH 43068-9009 180 East Broad Street Columbus, OH 43266-0573 Regional Administrator U.S. Nuclear Regulatory Commission Attorney General 801 Warrenville Road Department of Attorney General Lisle, IL 60523-4351 30 East Broad Street Columbus, OH 43216 Michael A. Schoppman Framatome ANP President, Board of County 1911 N. Ft. Myer Drive Commissioners of Ottawa County Rosslyn, VA 22209 Port Clinton, OH 43252 Resident Inspector President, Board of County U.S. Nuclear Regulatory Commission Commissioners of Lucas County 5503 North State Route 2 One Government Center, Suite 800 Oak Harbor, OH 43449-9760 Toledo, OH 43604-6506 Randel J. Fast, Plant Manager David Lochbaum, Nuclear Safety Engineer FirstEnergy Nuclear Operating Company Union of Concerned Scientists Davis-Besse Nuclear Power Station 1707 H Street NW, Suite 600 5501 North State - Route 2 Washington, DC 20006 Oak Harbor, OH 43449-9760 The Honorable Dennis J. Kucinich Dennis Clum United States House of Representatives Radiological Assistance Section Supervisor Washington, D.C. 20515 Bureau of Radiation Protection Ohio Department of Health The Honorable Dennis J. Kucinich, Member P.O. Box 118 United States House of Representatives Columbus, OH 43266-0118 14400 Detroit Avenue Lakewood, OH 44107
FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 255 License No.
NPF-3
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee) dated November 30, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 255, are hereby incorporated in the license. FirstEnergy Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 255 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3/4 4-5 3/4 4-5
REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with:
- a. A steam bubble,
- b. A water level between 45 and 228 inches. l APPLICABILITY: MODES 1 and 2.
ACTION:
With the pressurizer inoperable, restore the pressurizer to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or l be in at least HOT STANDBY with the control rod drive trip breakers open within the next 6 l hours. l SURVEILLANCE REQUIREMENTS 4.4.4 The pressurizer shall be demonstrated OPERABLE by verifying pressurizer level to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
DAVIS-BESSE, UNIT 1 3/4 4-5 Amendment No. 255
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 255 TO FACILITY OPERATING LICENSE NO. NPF-3 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION DOCKET NO. 50-346
1.0 INTRODUCTION
By letter dated November 30, 2001 (Ref. 1) pursuant to Title 10 of the Code of Federal Regulations (CFR) Section 50.90, FirstEnergy Nuclear Operating Company (FENOC),
requested an amendment to Operating License NPF-3 for the Davis Besse Nuclear Power Station (DBNPS), Unit 1. The license amendment request (LAR) revises the current DBNPS Technical Specification (TS) 3/4.4.4, Reactor Coolant System - Pressurizer. Specifically, the proposed TS changes would (1) reduce the pressurizer high level limit specified in limiting condition for operation (LCO) 3.4.4 from 305 inches to 228 inches, and (2) modify the action requirement, when the pressurizer is inoperable, by adding a statement, which allows for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the pressurizer to OPERABLE status before taking action to place the plant in HOT STANDBY.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TS are derived from the plant safety analyses.
The staff has reviewed the proposed changes for compliance with 10 CFR 50.36 and agreement with the precedent as established in NUREG-1430. In general, licensees cannot justify TS changes solely on the basis of adopting the model standard technical specifications (STS). To ensure this, the staff makes a determination that proposed changes maintain adequate safety. There are two classes of changes to the TS: (1) changes needed to reflect contents of the design basis, and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This LAR deals with both classes of changes: (1) revising the pressurizer high water limit reflects the contents of the design basis, and (2) providing a time limit for restoring pressurizer operability is a voluntary change that takes advantage of the content and preferred format of TS. In determining the acceptability of the revised pressurizer high water limit, the staff evaluated the licensees loss of feedwater transient analysis. In determining the acceptability of adding a time limit for restoring pressurizer operability, the staff used the accumulation of generically approved guidance in NUREG-1430, Revision 2, Standard Technical Specifications, Babcock and Wilcox Plants, dated October 10, 2001.
Licensees may revise the TS to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative, or provides clarification (i.e., no requirements are materially altered),
(2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
DBNPS TS LCO 3.4.4 specifies that, during Modes 1 and 2 operation, the pressurizer shall be operable with (a) a steam bubble, and (b) a water level between 45 and 305 inches. This LCO is intended to ensure that a steam bubble exists in the pressurizer prior to power operation to minimize the consequences of potential overpressure transients. The pressurizer high level limit permits pressure control equipment such as sprays and heaters to function as designed.
The high level limit also prevents filling the pressurizer, i.e., water solid, during anticipated transients, thus ensuring that the pressurizer code safety valves and pilot-operated relief valves can provide overpressure protection by steam relief rather than water relief. Although the prevention of water relief through code safety valves is not a requirement for compliance with a safety limit, it is a design basis because water relief could potentially challenge valve reliability.
The proposed change to LCO 3.4.4 to reduce the existing high pressurizer water level limit of 305 inches to 228 inches is more restrictive than the existing LCO. The need for the proposed reduction in the high pressurizer water level limit was identified by the licensee during a review of the design basis. The licensee determined that the high level limit of 305 inches did not provide enough steam volume to prevent the pressurizer from going water solid during a loss of feedwater (LOFW) event, which is the most severe anticipatory transient with respect to pressurizer insurge. The licensee desires to prevent the pressurizer from going water solid in order to avoid code safety valves and power operated relief valves (PORV) from controlling reactor coolant system (RCS) pressure by relieving water, rather than steam, since water relief could potentially damage the valves. The proposed high level limit of 228 inches will reduce the likelihood of pressurizer going water solid during the most anticipated transient; thereby reducing the potential damage to the code safety relief valves and the PORV. The proposed change to TS 3/4.4.4 involving decreasing the pressurizer high level limit is more restrictive than the current limit.
The licensee performed an LOFW transient analysis with an initial pressurizer water level at a 220 inches, which is the nominal controller setpoint for power operation. The analysis result showed that when the pressurizer reached its peak level during the transient, 26 cubic feet of steam volume existed in the pressurizer. This 26 cubic feet of available steam space corresponds to 8 inches of initial pressurizer level. Hence the new high level limit of 228 inches is established to ensure that the pressurizer will not go water solid during a LOFW event initiated when operating with pressurizer level below this limit. Since the LOFW event is the most severe anticipated transient in terms of insurge into the pressurizer, the staff concludes that the high water level limit of 228 inches will provide assurance of no water release through the code safety valves during anticipatory transients, and is acceptable.
The licensee also proposed to revise the ACTION requirement, in the event that the pressurizer is inoperable, by adding a statement allowing for up to one hour to restore the pressurizer to OPERABLE status before taking action to place the plant in HOT STANDBY within the next
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The pressurizer inoperability can be due to complete loss of steam bubble in the pressurizer, or due to the water level higher than 228 inches or lower than 45 inches. In the event pressurizer water level exceeds 228 inches, the STS for Babcock & Wilcox designed plants (NUREG-1430) allows for one hour to restore the pressurizer to OPERABLE status. The staff also considers that the high water level is established to prevent water release through the safety valve to ensure valve reliability, rather than for compliance of safety limit. Therefore, allowing one hour to restore pressurizer operability would have an insignificant effect on public safety, and is acceptable. Since the complete loss of steam bubble in the pressurizer will be preceded by a condition of the pressurizer water level exceeding the high water level limit of 228 inches, this inoperability condition is covered by the high level limit.
The pressurizer low water level limit is based on providing enough water volume to prevent a reactor coolant system low pressure condition that would actuate the reactor protection system (RPS) or the engineered safety feature actuation system (ESFAS). Should an RCS depressurization event occur while the pressurizer water level is below the 45-inch low level limit, the plant will still be protected by the RPS and ESFAS. Therefore allowing up to one hour to restore to the OPERABLE status for the low level limit noncompliance will have no safety significance, and is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official has no comments.
5.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (68 FR 37578). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The staff has reviewed the proposed changes to DBNPS TS 3.4.4 to (1) reduce the pressurizer high level limit from 305 inches to 228 inches, and (2) revise the Action requirement for inoperable pressurizer by allowing one hour to restore the pressurizer to OPERABLE status before taking action to place the plant in HOT STANDBY. Based on the evaluation described in Section 2.0, the staff concludes these changes acceptable.
The staff has concluded, based on the considerations above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation into proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCE
- 1. Letter from Guy G. Campbell, FirstEnergy, to US Nuclear Regulatory Commission, Davis-Besse Nuclear Power Station, License Amendment Application to Revise Technical Specification 3/4.4.4, Reactor Coolant System - Pressurizer, to Adopt New Pressurizer Level Requirements (License Amendment Request No. 01-0012), November 30, 2001.
Principal Contributors: P. Hearn Y. Hsii Date: August 12, 2003