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Category:Letter
MONTHYEARIR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 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 ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter 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 L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230902023-08-0101 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 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 2024-08-01
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24057A0772024-03-0101 March 2024 Conforming License Amendments - Enclosure 1 ML24057A0782024-03-0101 March 2024 Amendments to Indemnity Agreements - Enclosure 2 ML23237B4412023-09-29029 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 ML0604102252006-03-0202 March 2006 Amendment License Application to Revise TS 3/4.8.1.1 A.C.Sources-Operating ML0604005522006-03-0202 March 2006 License Amendment 274 Framatome Mark B-HTP Fuel Design for Cycle 15 ML0526403932006-02-0707 February 2006 Licensing Amendment - Issuance of Amendment Administrative Controls 2024-03-01
[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 ML14030A5742014-03-31031 March 2014 Safety Evaluation Concerning Comprehensive Pump Testing Relief Request (TAC No. MF0756) (L-13-067) ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) 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] Category:Technical Specifications
MONTHYEARML22210A0102022-09-16016 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 ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme 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 ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels ML1208604472012-04-18018 April 2012 Issuance of Amendment Modification of the Special Visual Inspection Requirement of TS 5.5.8 Steam Generator Program L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011 License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program. L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0822706662008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 10, Revision 1, ITS Section 3.5, Emergency Core Cooling Systems L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations2008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations ML0822706612008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 1, Revision 1, Application of Selection Criteria to the Dbnps Technical Specifications ML0822706622008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 2, Revision 1, Generic Determination of No Significant Hazards Consideration and Environmental Assessment ML0822706672008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 16, Revision 1, ITS Chapter 5.0, Administrative Controls ML0822706702008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 13, Revision 1, ITS Section 3.8, Electrical Power Systems ML0822706692008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 12, Revision 1, ITS Section 3.7, Plant Systems ML0822706652008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 8, Revision 1, Section 3.3 - Instrumentation ML0822706642008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 4, Revision 1, ITS Chapter 2.0, Safety Limits ML0822706632008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request Volume 3, Revision 1, ITS Chapter 1.0, Use and Application ML0822706582008-08-0707 August 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications to Improved Technical Specifications - Volumes 1, 2, 3, 4, 8, 10, 12, 13, 14, and 16 ML0818306382008-06-30030 June 2008 Tech Spec Pages for Amendment 278 Regarding Measurement Uncertainty Recapture Power Uprate ML0826005772008-05-30030 May 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits ML0814804652008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 5, (Revision 1), Section 3.0 - LCO and SR Applicability ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features L-08-065, Response to Request for Additional Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate2008-02-20020 February 2008 Response to Request for Additional Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate ML0729601812007-10-17017 October 2007 Technical Specifications, Issuance of Amendment Administrative Control of Penetrations During Refueling ML0722004632007-08-0303 August 2007 Volume 5, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.0 LCO and SR Applicability. ML0722004512007-08-0303 August 2007 Submittal of License Amendment Request No. 06-0003 to Revise Current Technical Specifications to the Improved Technical Specifications ML0722004862007-08-0303 August 2007 Volume 17, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Current Technical Specification Markup in CTS Order. ML0722004852007-08-0303 August 2007 Volume 16, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 5.0 Administrative Controls. ML0722004542007-08-0303 August 2007 Volume 1, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Application of Selection Criteria. ML0722004562007-08-0303 August 2007 Volume 2, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Generic Determination of No Significant Hazards Consideration and Environmental Assessment. ML0722004592007-08-0303 August 2007 Volume 3, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 1.0 Use and Application. ML0722004612007-08-0303 August 2007 Volume 4, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 2.0 Safety Limits. ML0722004832007-08-0303 August 2007 Volume 15, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 4.0 Design Features. ML0722004662007-08-0303 August 2007 Volume 6, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 3.1 Reactivity Control Systems. ML0722004682007-08-0303 August 2007 Volume 7, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.2 Power Distribution Limits. ML0722004702007-08-0303 August 2007 Volume 8, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.3 Instrumentation. ML0722004722007-08-0303 August 2007 Volume 9, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.4 Reactor Coolant System. 2022-09-16
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-6001 April 18, 2012 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1-ISSUANCE OF AMENDMENT RE: MODIFICATION OF THE SPECIAL VISUAL INSPECTION REQUIREMENT OF TECHNICAL SPECIFICATION 5.5.8, "STEAM GENERATOR (SG) PROGRAM" (TAC NO. ME6296)
Dear Mr. Allen:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 285 to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit No.1 (DBNPS). The amendment revises the technical specifications (TSs) in response to your application dated May 20,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11144A289), as supplemented by letter dated February 7,2012 (ADAMS Accession No. ML 12039A199).
This amendment revises the TS 5.5.8.g requirement for a special visual inspection of the secured internal auxiliary feedwater header (AFWH) for the steam generators (SGs) to be condition-based instead of frequency-based.
Specifically, TS 5.5.8.g requires visual inspection of the secured internal AFWH, header to shroud attachment welds, and external header thermal sleeves of the SGs at DBNPS during the third period of each 10-year inservice inspection interval (lSI). With the proposed change, if eddy current inspections (required by TS 5.5.8.d.5) identify any SG peripheral tube to secured internal AFWH gaps less than % inches or there is evidence that the header is degrading or has moved, then the TS 5.5.8.g visual inspections shall be performed on the affected SG.
B. Allen A copy of the Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-346
Enclosures:
- 1. Amendment No. 285 to NPF-3 2. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555"()001 FIRSTENERGY NUCLEAR OPERATING COMPANY AND FIRSTENERGY NUCLEAR GENERATION CORP. DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE NPF-3 Amendment No. 285 Facility Operating License No. NPF-3 The U.S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment filed by FirstEnergy Nuclear Operating Company (FENOC) et al. (the licensee), dated May 20,2011 as supplemented by letter dated February 7, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 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. 285, are hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ja b I. Zim man, Chief PIt Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: .April 18, 2012 ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Facility Operating License (FOL) and Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Insert FOL NPF-3 FOL NPF-3 Page 4 Page 4 TSs TSs 5.5-8 5,5-8
-4 2.C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level FENOC is authorized to operate the facility at steady state reactor core power levels not in excess of 2817 megawatts (thermal).
Prior to attaining the power level, Toledo Edison Company shall comply with the conditions identified in Paragraph (3) (0) below and complete the preoperational tests, startup tests and other items identified in Attachment 2 to this license in the sequence specified.
Attachment 2 is an integral part of this license. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 285, are hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications. Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the license or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission: FENOC shall not operate the reactor in operational Modes 1 and 2 with less than three reactor coolant pumps in operation. (b) Deleted per Amendment 6 (c) Deleted per Amendment 5 Amendment No. 285 Programs and Manuals 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued) Special visual inspections:
If the inspections required by TS 5.5.8.d.5 identify any peripheral tube to secured internal auxiliary feedwater header gaps less than 1/4 inch, or there is evidence that the header is degrading or has moved, visual inspections of the secured internal auxiliary feedwater header, header to shroud attachment welds, and external header thermal sleeves shall be performed on the affected SG through the auxiliary feedwater injection penetrations.
5.5.9 Secondary
Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation.
The program shall include: Identification of a sampling schedule for the critical variables and control pOints for these variables; Identification of the procedures used to measure the values of the critical variables; Identification of process sampling points; Procedures for the recording and management of data; Procedures defining corrective actions for all off control point chemistry conditions; and A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action. 5.5.10 Ventilation Filter Testing Program (VFTP) A program shall be established to implement the following required testing of safety related filter ventilation systems in accordance with Regulatory Guide 1.52, Revision 2, ANSIIASME N510-1980, and ASTM D 3803-1989. Demonstrate for each of the safety related systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 1.0% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSIIASME N510-1980 at the system flowrate specified below. Safety Related Ventilation Flowrate (cfm) Station Emergency Ventilation System (EVS) <:: 7200 and s 8800 Control Room Emergency Ventilation System <:: 2970 and s 3630 (CREVS) 5.5-8 Amendment 285 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 285 TO FACILITY OPERATING LICENSE NO. NPF-3 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 DOCKET NO. 50-346
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated May 20, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11144A289), as supplemented by letter dated February 7,2012 (ADAMS Accession No. ML 12039A 199) FirstEnergy Nuclear Operating Company, et al. (the licensee) requested changes to the Technical Specifications (TSs) for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS). The proposed change would revise TS 5.5.8.g to perform the special visual inspections based on a condition rather than a specific frequency.
Specifically, TS 5.5.8.g requires visual inspection of the secured internal auxiliary feedwater header (AFWH), header to shroud attachment welds, and external header thermal sleeves of the steam generators (SGs) at DBNPS during the third period of each 10 year inservice inspection interval (lSI). With the proposed change, if eddy current inspections (required by TS 5.5.8.d.5) identify any SG peripheral tube to secured internal AFWH gap less than % inches or there is evidence that the header is degrading or has moved, then the TS 5.5.8.g visual inspections shall be performed on the affected SG. The February 7, 2012 supplement provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's initial proposed finding of no significant hazards consideration determination.
2.0 BACKGROUND
DBNPS has two Babcock and Wilcox once-through SGs, designated as 1-B and 2-A Each SG has approximately 15,500 Alloy 600 tubes in the mill-annealed condition.
The tubes have a nominal outside diameter of 0.625 inches and a nominal wall-thickness of 0.037 inches. Both SG 1-B and 2-A contain tubes with sleeves and tubes with shop re-rolls.
-2 During a refueling outage in 1982, eddy current inspections revealed indications of tube damage in some of the SG peripheral tubes. Follow-up visual inspections in the secondary side of the SGs confirmed that the internal AFWH in both SGs had been dislodged and severely deformed, resulting in damage to some of the peripheral tubes in both SGs. As a result of the extensive damage to the internal AFWHs, the licensee secured and abandoned-in-place the internal AFWH in each SG. On September 30, 1983 (ADAMS Accession No. ML021160474), the NRC issued a license amendment that required, in part, the licensee to perform a special visual inspection on the secured internal AFWH, the shroud attachment welds, and the external header thermal sleeves.
3.0 REGULATORY EVALUATION
The tubes within a SG function as an integral part of the reactor coolant pressure boundary (RCPB) and, in addition, serve to isolate radiological fission products in the primary coolant from the secondary coolant and the environment.
For the purposes of this safety evaluation, tube integrity means that the tubes are capable of performing these functions in accordance with the plant design and licensing basis. Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to the integrity of the SG tubing. Specifically, the General Design Criteria (GDC) in Appendix A to 10 CFR Part 50 states that the RCPB shall have "an extremely low probability of abnormalleakage
...and of gross rupture" (GDC-14), "shall be designed with sufficient margin" (GDC-15 and -31), shall be of "the highest quality standards practical" (GDC-30), and shall be designed to permit "periodic inspection and testing ... to assess ... structural and leaktight integrity" (GDC-32).
To this end, 10 CFR 50.55a specifies that components which are part of the RCPB must meet the requirements for Class 1 components in Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Requirements of 10 CFR 50.55a state, in part, that throughout the service life of a pressurized water reactor (PWR) facility like DBNPS, ASME Code Class 1 components meet the requirements, including design and access provisions and pre-service examination requirements, in Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the ASME Code.Section XI requirements pertaining to inservice inspection of SG tubing are augmented by additional SG tube surveillance requirements in the TSs. As part of the plant licensing basis, applicants for PWR licenses are required to analyze the consequences of postulated design-basis accidents such as an SG tube rupture and main steamline break. These analyses consider the primary-to-secondary leakage through the tubing which may occur during these events and must show that the offsite radiological consequences do not exceed the applicable limits of the 10 CFR Part 100.11 guidelines for offsite doses (or 10 CFR 50.67, as appropriate), GDC-19 criteria for control room operator doses, or some fraction thereof as appropriate to the accident, or the NRC-approved licensing basis. It states in 10 CFR 50.36(b), in part, that the TSs will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to 10 CFR 50.34. It also states in 10 CFR 50.36(c)(5) that TSs shall contain administrative controls "relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." As discussed below, TS 5.5.8 establishes a SG program to ensure that tube integrity is maintained to assure safe operation of DBNPS. TS 5.5.8 for DBNPS requires that a SG Program be established and implemented to ensure that SG tube integrity is maintained.
The DBNPS TSs are modeled after Technical Specification Task Force Traveler 449 (TSTF-449), "Steam Generator Tube Integrity," Revision 4. Tube integrity is maintained by meeting specified performance criteria for structural and leakage integrity consistent with the plant design and licensing bases. TS 5.5.8 requires a condition monitoring assessment be performed during each outage during which the SG tubes are inspected, plugged or repaired to confirm that the performance criteria are being met. TS 5.5.8 also includes provisions regarding the scope, frequency, and methods of SG tube inspections.
4.0 TECHNICAL
EVALUATION The licensee proposed to change the TS 5.5.8.g requirement for a special visual inspection of the secured internal AFWH to be condition-based instead of frequency-based.
The licensee is currently required to perform the eddy current inspections required by TS 5.5.8.d.5 on the peripheral SG tubes during every refueling outage. These inspections are intended to detect degradation of inservice tubing due to interaction with the secured internal AFWH. The licensee has proposed that if the eddy current inspections identify a gap of less than X inch between any SG peripheral tube and the secured internal AFWH, or there is evidence that the header is degrading or has moved, then the visual inspections of the secured internal AFWH, the header-to-shroud attachment welds, and the external header thermal sleeves shall be performed on the affected SG, through the auxiliary freshwater injection penetrations.
This would replace the current requirement to do these inspections during the third period of each 10-year lSI. The licensee stated that modifying this requirement is predicated on historically acceptable visual and eddy current inspection results for both SGs and an evaluation of changes to operational conditions.
After performing a baseline special visual inspection in 1983, the licensee performed the special visual inspection of the internal AFWH during the next two refueling outages and during the third period of each 10-year lSI interval.
The special visual inspection program included inspecting the internal AFWH and the internal AFWH-to-shroud welds for degradation, and inspecting the external header thermal sleeves for indications of cracking.
In addition to these visual inspections, the licensee has also performed eddy current inspections on a minimum of 150 peripheral tubes in each SG, during every refueling outage since the external AFWHs were installed.
The eddy current inspection technique used by the licensee was developed and qualified with the specific purpose of detecting if the internal AFWH had moved to within X inch of any of the inspected peripheral tubes. To date, several special visual inspections have been performed on SGs 1-B and 2-A. Four small linear indications were found on one of the thermal sleeves in SG 1-B in 1984. The licensee reported that the indications appeared to be a result of the visual inspection process (Le., disassembly and reassembly).
The sleeve was reworked and no other indications have been reported as a result of the special visual inspections in SG 1-8. For SG 1-8, the last special visual inspection was performed in 2010, and no other special visual inspections are scheduled before the planned replacement of the SG in 2014. No indications have ever been reported as a result of the special visual inspections in SG 2-A The last special visual inspection of SG 2-A was performed in 1998 and only one special visual inspection is scheduled before the planned replacement of the SG in 2014. The eddy current inspections have been performed on the peripheral tubes of both SGs during every refueling outage since 1983, and no indications of internal AFWH movement have been reported.
In support of a turbine header pressure modification in 2007, SGs 1-8 and 2-A were evaluated by the licensee for the expected changes in operational conditions.
The licensee's evaluations concluded that the increase in header pressure from 870 pounds per square inch gauge (psig) to 880 psig resulted in a negligible effect on flow-induced vibration and would not significantly impact the SGs. In support of a reactor power uprate in 2008, SGs 1-8 and 2-A were further evaluated for the expected changes in operational conditions.
The licensee's evaluations concluded that the approximate
1.6 percent
reactor power increase resulted in a negligible effect on flow-induced vibration and would not significantly impact the SGs. No other modifications with potential to affect the SGs, the secured internal AFWHs, or the external header thermal sleeves, were identified by the licensee.
The licensee performed special visual inspections of steam generator 1-8 in 2010, and eddy current inspections of SGs 1-8 and 2-A in 2010, and concluded that the acceptable findings of these inspections validated both the header pressure change and power uprate evaluations.
The NRC staff concludes that the historical visual and eddy current inspection results demonstrate that the internal AFWH is adequately secured. In addition, the NRC staff concludes that the requirement to inspect the peripheral SG tubes by eddy current techniques and the proposed requirement to perform visual inspections of the internal AFWH, the internal AFWH-to-shroud welds, and the external header thermal sleeves if there is evidence of less than a }'4 inch gap between any SG peripheral tube and the secured internal AFWH, or there is evidence that the header is degrading or has moved, provides reasonable assurance that the safety functions of the SG will not be compromised.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official had no comments.
6.0 ENVIRONMENTAL
CONSIDERATION 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 NRC 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 (76 FR 58306; September 20,2011).
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.
7.0 CONCLUSION
Based on the above considerations, the NRC staff finds the licensee's proposed change to switch from frequency-based special visual inspections to condition-based special visual inspections in TS 5.5.8.g acceptable.
The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's 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. Principal Contributor:
AJohnson, NRR Date: April 18, 2012 B. Allen A copy of the Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, I RAJ Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. Amendment No. 285 to NPF-3 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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