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MONTHYEARML0929605752009-10-23023 October 2009 Acceptance Review Results for Davis-Besse LBB LAR (ME2310) Project stage: Acceptance Review L-09-319, Request to Withhold from Public Disclosustructural Integrity Associates, Inc. Report Number 0800368.404, Revision 0, July 20, 20092009-12-0303 December 2009 Request to Withhold from Public Disclosustructural Integrity Associates, Inc. Report Number 0800368.404, Revision 0, July 20, 2009 Project stage: Other ML0935205492010-01-0505 January 2010 RAI Related to License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Section Project stage: RAI ML1002501322010-01-11011 January 2010 0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B Project stage: Other L-10-027, Response to Request for Additional Information Related to License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds2010-01-20020 January 2010 Response to Request for Additional Information Related to License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds Project stage: Response to RAI ML1002513792010-02-0101 February 2010 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML1003506402010-02-0404 February 2010 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License Project stage: Other ML1003506612010-02-16016 February 2010 Individual 30-day Proposed Notice of Consideration of Issuance of Amendment to License to Support Application of Optimized Weld Overlays Project stage: Request 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 Project stage: Approval ML1009705492010-04-0909 April 2010 Corrections of Typographical Errors Amendment No. 281 and Safety Evaluation Project stage: Approval 2010-01-05
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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
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UNrrED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 April 9, 2010 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
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - CORRECTIONS OF TYPOGRAPHICAL ERRORS RE: AMENDMENT NO. 281 AND SAFETY EVALUATION (TAC NO. ME2310)
Dear Mr. Allen:
On March 24, 2010, the U.S. Nuclear Regulatory Commission issued Amendment No. 281 to Facility Operating License No. NPF*3 for the Davis-Besse Nuclear Power Station, Unit 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100640506). The amendment approved changes to the current licensing basis for Davis Besse Nuclear Power Station, Unit 1 (DBNPS) associated with the leak-before-break (LBB) evaluation for the reactor coolant pump suction and discharge nozzle dissimilar metal welds.
FirstEnergy Nuclear Operating Company staff subsequently identified typographical errors in the Amendment and repspective safety evaluation. Specifically, the corrections are as follows:
Amendment No. 281 to NPF*3, page 1, Section 2, the last sentence should read "September 28, 2009..." and not "September 28,2010.... " Safety Evaluation, page 3, Section 3.2, first paragraph, "electronic e-mail dated" has been added in from of the statement "December 15, 2009 (ADAMS Accession No. ML100040016) ..." to clarify that it is an e-mail and not a letter.
Safety Evaluation, page 8, 5th paragraph, first sentence, the word "incorpor+ated" should read "incorporate." Safety Evaluation, page 11, first paragraph: second full sentence should read "have performed any ..." and not "has perform any .... " Safety Evaluation, page 11, 6th paragraph, last sentence should read "maximum number of crack sizes ..." and not "maximum number of crack size ... ". Safety Evaluation, page 13, Section 3.3.6, Item (1), 2nd sentence should read "SRP Section 3.6.3" and not "SPR Section 3.6.3." Safety Evaluation, page 14, Section 5.0, instances of the word "amendments" have been changed to "amendment." Safety Evaluation, page 16, Section 7.0, 2nd paragraph, last sentence should read "issuance of the amendmenL" and not "issuance of the amendments .... "
The NRC staff determined that these typographical errors were inadervently introduced. The proposed corrections do not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public.
B. Allen -2 Corrected Amendment No. 281 to NPF-3 page 1 and safety evaluation pages 3, 8, 11, 13, 14 and 16 are enclosed. If you or your staff have any questions, please call me at 301-415-3867 Sincerely, ichael Mahoney, oject Manager Plant licensing B anch 111-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
Amendment 1\10. 281 to I\IPF-3 cc w/encls: Distribution via listserv
ENCLOSURE CORRECTED PAGE 1 OF AMENDMENT NO. 281 FACILITY OPERATING LICENSE NO. NPF-3 DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1
-AND CORRECTED PAGES 3, 8,11,13,14 AND 16 OF SAFETY EVALUATION
FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 281 License No. NPF-3
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by FirstEnergy Nuclear Operating Company (FENOC. the licensee). dated September 28,2009, as supplemented by letter dated January 20, 2010. 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; 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended to authorize revision of the current licensing basis for Davis-Besse Nuclear Power Station, Unit 1, as set forth in the application for amendment by the licensee; dated September 28, 2009, as supplemented by letter dated January 20, 2010.
- 3 weld overlay installation on the lBB-approved RCP piping changes, the piping geometry, and the design basis of the original lBB evaluation. SRP Section 3.6.3 specifies that the worst loads should be applied to the worst pipe location(s) to demonstrate that safety margins in SRP Section 3.6.3 are satisfied. Normally, a lBB evaluation analyzes several pipe locations with the worst load combinations to ensure that all possible worst-case scenarios have been addressed.
However, when a weld overlay is installed on a DMW, it is not clear whether the worst-case location with the worst-case load combination in the original lBB evaluation would bound the overlaid DMW. Therefore, licensees will update their original lBB evaluation to show that the design basis is maintained after weld overlay installation (i.e., demonstrate the overlaid DMW satisfies the safety margins). Licensees will revise their Updated Final Safety Analysis Report after receipt of the safety evaluation to document the resolution of this issue.
The RCP suction nozzle is directly welded to a pipe elbow with a DMW without a safe-end. The RCP suction nozzle is made of cast austenitic stainless steel (CASS) with a nominal inside diameter of 28 inches. The elbow is made of carbon steel and its inside surface is clad with stainless steel. The licensee will apply a FSWOl to a portion of the suction nozzle, DMW, and a portion of the elbow.
The RCP discharge nozzle is welded to a stainless steel safe-end with a stainless steel weld.
The downstream of the safe-end is welded to the carbon steel pipe elbow with a DMW. The licensee proposed to apply either a FSWOl or OWOl on a portion of the safe-end, DMW and a portion of the elbow. The discharge nozzle will not be covered with the weld overlay.
3.2 Weld Overlay Design By letter dated January 30,2009 (ADAMS Accession No. Ml090350070), with supplements dated July 13, 2009 (ADAMS Accession No. Ml091950627), November 23, 2009 (ADAMS Accession No. Ml093360333). and electronic e-mail dated December 15. 2009 (ADAMS Accession No. Ml1 00040016). the licensee submitted Relief Requests RR-A32 and RR-A33 for the OWOl and FSWOl designs, respectively, to be applied on the DMWs of the RCP suction and discharge nozzles.
By letter dated January 21,2010, the NRC approved Relief Request RR-A33 for the FSWOl design (ADAMS Accession No. Ml100080573). By letter dated January 29,2010. the NRC approved Relief Request RR-A33 for the OWOl design (ADAMS Accession No. ML100271531).
The requirements for the design, stress analyses, crack growth calculations, and examinations of the FSWOl and OWOl are discussed in detail in the above relief requests and respective NRC's safety evaluations. The weld overlay design is discussed herein briefly to demonstrate that PWSCC, an active degradation mechanism affecting the Alloy 82/182 DMW of the subject RCP piping, will be mitigated by the weld overlay and it will no longer be an active degradation mechanism; thereby, the RCP piping will continue to satisfy the screening criteria of SRP 3.6.3.
3.2.1 Weld Overlay Thickness Sizing The weld overlay thickness affects the critical crack size and leakage calculations in the lBB evaluation. The overlay thickness is derived based on several assumptions and requirements of the American Society of Mechanical Engineers (ASME) Code. The licensee evaluates a postulated or an actual crack in the DMW in accordance with flaw evaluation rules of the ASME Code,Section XI, "Rules for Inservice Inspection (lSI) of Nuclear Power Plant Components."
The licensee derived the Z-factor for the Alloy 82/182 DMW from Reference 4.
The Z-factors for ferritic (carbon steel) base metals and associated weld metals, and for austenitic weld materials fabricated using SMAW or SAW process are derived from the ASME Code,Section XI, Appendix C. For conservatism, the licensee applied the Z-factor for the SAW to the cast austenitic stainless steel RCP casing. The weld overlay is fabricated with the gas tungsten arc welding process with Alloy 52M as the weld metal. This weldment (weld overlay) has high fracture toughness and the Z-factor is 1.0 per the ASME Code,Section XI, Appendix C.
The NRC staff finds that the Z-factors used in the updated lBB evaluation are acceptable because they were derived from the ASME Code,Section XI, Appendix C or recognized studies such as Reference 4.
The NRC staff questioned whether internal pressure was actually applied to the crack surface in calculating the flaw stability. In letter dated January 20,2010, the licensee responded that although the updated lBB evaluation included the terms that could be used for evaluating crack face pressure, crack face pressure was not used in calculating flaw stability or leakage. This is consistent with the net-section-collapse analysis equations that are provided in SRP 3.6.3 and in the ASME Code,Section XI, Appendix C. The NRC staff finds that internal pressure on the crack surface of the DMW and weld overlay does not affect the result significantly. Therefore, the NRC staff does not object that the internal pressure was not applied to the crack face.
The NRC staff asked the licensee to discuss whether the saturated fracture toughness (worst case conditions) of the CASS material of the RCP nozzles was used in the updated lBB evaluation. In letter dated January 20, 2010, the licensee responded that the saturated fracture toughness of the CASS material of the RCP nozzles was used in the updated lBB evaluation in accordance with ASME Section XI Code Case N-481, "Alternative Examination Requirements for Cast Austenitic Pump CasingsSection XI, Division 1." The saturated fracture toughness is determined from actual material certified material test reports (CMTRs). The licensee selected the lower bound fracture toughness of the worst DBNPS pump casing considering thermal embrittlement. Using the material properties from the CMTRs, the licensee calculated the saturation impact energy (CVsat) used in determining the J-R curve (J-Integral resistance curves for stable crack growth) and subsequently, the fracture toughness of the CASS material.
The NRC staff approved Code Case N-481 to be used in RG 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 14. ASME annulled Code Case N-481 in March 2004, and the provisions of the code case are incorporated in the ASME Code.
Subsequently the code case is not approved for use in RG 1.147, Revision 15. Therefore, Code Case N-481 is no longer permitted to be used. However, the licensee used the lower bound fracture toughness of the worst DBNPS pump casing material heats considering thermal embrittlement. Therefore, the NRC staff finds that the licensee has appropriately considered thermal embrittlement of the CASS RCP nozzles in the flaw stability analYSis.
The licensee calculated various critical crack sizes for the FSWOl design from 45 to 58 inches in circumference. For the OWOl design, the licensee calculated various critical crack sizes from 39 inches to 52 inches.
The NRC staff noted that the critical crack sizes (lengths) for the FSWOl are comparable to the critical crack size for the OWOl design for the RCP discharge nozzle. In letter dated January 20,2010, the licensee explained that at the RCP discharge nozzle, there is little difference in thickness between the weld overlay thicknesses evaluated with the minimum and
- 11 calculating leakage in through-wall cracked piping, and has been used in numerous LBB evaluations that the NRC has approved. The licensee stated further that PICEP was verified by comparison to a large number of tests for leakage through cracks. However, the licensee recognizes that neither industry nor the NRC have performed any tests to verify leak rates through weld overlaid pipe or through PWSCC cracked piping. The licensee noted that there may be uncertainties in the leakage calculations associated with LBB, thus, a factor of 10 is applied between the calculated leakage rate and the leakage detection capability in nuclear plants applying LBB.
The licensee stated that it used a crack morphology that was verified by early EPRl/Battelle work to justify the PICEP computer program. The values used provided a good mean prediction of leakage for a large number of tests. NUREG/CR-6004, "Probabilistic Pipe Fracture Evaluations for Leak-Rate Detection Applications," NRC, April 1995, provides data on microscopic measurements to quantify flow path morphology and is the basis of a modified model that is reasonable for predicting leakage for the overlaid DMW.
The original LBB evaluation assumed fatigue cracking with a crack morphology roughness of 0.000197 with no turns. However, in the updated LBB evaluation, the licensee assumed that the morphology associated with PWSCC crack propagation parallel to the long direction of the dendritic grains would be applicable. The PWSCC crack usually results in various 45 and 90 degree turns as it propagates through the pipe wall thickness. The licensee obtained the following data from the NRC-sponsored research on PWSCC (Reference 6), as input to the leakage calculation.
Local roughness, inches = .000663778 Global roughness, inches = .0044842 Number of 90 degree turns per inch = 150.87 Global flow path length to thickness ratio = 1.009 Global plus local flow path length to thickness ratio =1.243 The average numbers of turns (reported as 90 degree turns only) for a typical PWSCC crack is 150.87. However, the licensee modified the number ofturns to derive the effective (equivalent) number of turns based on the crack opening displacement and roughness to simulate the total path fluid flow resistance in the original DMW and overlay. The licensee also developed equivalent roughness and equivalent flow path length for flow through a complex crack.
The licensee stated that a series of 20 crack sizes were evaluated, so that the relationship between crack size and crack opening displacement will be determined at closely spaced sample points for more accurate interpolation over a range that bounds the crack size of interest.
PICEP has a limit of 20 crack sizes between zero and a maximum crack size, so the maximum number is used. The NRC staff finds it is acceptable that the licensee used the maximum number of crack sizes in PICEP.
Under normal operation conditions of the RCP piping, the leakage may occur in a two-phase condition (I.e., a mixture of steam and water) at the exit. The NRC staff asked the licensee to clarify whether the two-phase flow condition has been considered in the leak rate calculation. In letter dated January 20, 2010, the licensee responded that the leakage calculation in PICEP considers flashing to two-phase condition in the craCk, such that a two-phase mixture will exist at the exit. In PICEP, the mass flow rate (for example Ib/sec) is converted to a volumetric flow rate (gpm) and is output at 200 degrees Fahrenheit (F). The licensee stated that the fluid that leaked
- 13 The NRC staff finds that the leakage methodology in the updated LBB evaluation is more up-to-date in its prediction than the leakage methodology used in the original LBB evaluation because of the research that has been performed since the 1980's. PICEP does not provide for leakage through a composite flow path such as flow through the Alloy 82/182 base material and Alloy 52 weld overlay. To address this consideration, the licensee derived a set of input parameters to simulate the composite flow path through the PWSCC portion of the assumed through wall crack in the base metal and fatigue portion of the crack in the weld overlay.
In the 1980's, the NRC staff specified a margin of 10 for leak rates recognizing the uncertainties in the leakage prediction. At present, the NRC staff finds that PICEP is acceptable for the analysis of the overlaid DMW when appropriate crack modeling and conservative input parameters for the crack morphology are used. The NRC staff finds further that the licensee's PICEP input parameters provide a reasonable simulation of flow through the composite flow path assumed for the leakage calculation and are, therefore, acceptable.
3.3.5 Comparison of LBB Evaluations The licensee compared the leakage flaw sizes calculated by the methodology in the updated LBB evaluation with the leakage flaw sizes calculated in the original LBB evaluation to determine any significant deviations between the two methodologies. The licensee used the method in the updated LBB evaluation to calculate the leakage flaws for the same straight pipe and elbow locations that were the subject of investigation in the original LBB evaluation. The results show that the leakage flaw sizes calculated by the updated LBB methodology are consistently smaller than the leakage flaw size calculated in the original LBB evaluation by approximately 15 percent.
The licensee explained that the differences may be attributed to the Ramberg-Osgood parameters used in the updated LBB evaluation, which were not used in the original LBB evaluation. The licensee concludes that the results suggest that the methodology used in the updated LBB evaluation is comparable to the methodology used in the original LBB evaluation.
The NRC staff finds that the differences in leakage flaw sizes between the two methodologies are not unexpected considering the differences in input parameters (use of Ramberg-Osgood parameters) and methodology (EPFM vs. limit load).
In terms of critical flaw size methodology, the original LBB evaluation determined critical flaw sizes based on the EPFM method. The updated LBB evaluation used a modified limit load methodology (two different materials) with the application of Z-factors in accordance with the ASME Code,Section XI, Appendix C. The NRC staff finds that the methodology in the updated LBB evaluation has used appropriate input parameters such as material properties and configurations and applied them to an appropriate model. Although uncertainties exist in the leak rate analysis of a composite overlaid DMW configuration, the margin available on leakage compensates for these uncertainties.
3.3.6 Summary The NRC staff finds the updated DBf\IPS LBB evaluation acceptable because:
(1) The licensee demonstrated by weld residual stress analysis that the weld overlay will mitigate PWSCC in the DMW. This satisfied the screening criteria of SRP Section 3.6.3.
(2) The critical crack size is more than twice the leakage crack size of the overlaid DMW; therefore, the safety margin of 2 specified by SRP 3.6.3 is satisfied.
- 14 (3) The leak rate from the leakage crack size is more than 10 times of the RCS leakage detection system capability of 1 gpm; therefore, the safety margin of 10 on leakage specified by SRP 3.5.3 is satisfied.
(4) The licensee performed a plant-specific and component-specific LBB evaluation and used appropriate input parameters and methodology.
4.0 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.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility's components 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 effluents 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.
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.
5.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION (NSHCD)
The commission may issue the license amendment before the expiration of the 50-day period provided that its final determination is that the amendment involves no significant hazards consideration. This amendment is being issued prior to the expiration of the 50-day period.
Therefore, a final finding of no significant hazards consideration follows.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91 (a), the licensee has provided its analysis of the issue of no significant hazards consideration which is presented below.
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The applicable accident is a Large Break Loss of Coolant Accident (LBLOCA). Since the application of [optimized weld overlays] OWOLs or [full structural weld overlays]
- 16 critical flawsize and the leakage flaw size. Although the longer flow path and considerations of crack morphology for the Alloy 82/182 weld location reduces leakage somewhat for a given through-wall flaw, the larger critical flaw size following application of the weld overlay allows for increased leakage margin. The evaluation described above demonstrates that these welds will perform as originally intended and that the adverse effects of PWSCC will be mitigated. Therefore, the proposed lBB update does not involve a significant reduction in a margin of safety. Based on the above, FENOC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c),
and, accordingly, a finding of "no significant hazards consideration" is justified.
As documented above, the proposed change does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and based on this review, determined that the three standards of 10 CFR 50.92 are satisfied. Therefore, the NRC staff has determined that the amendment involves no significant hazards consideration.
7.0 CONCLUSION
On the basis of its review of the updated DBNPS lBB evaluation, the NRC staff finds that the licensee has demonstrated that (1) the FSWOl and OWOl will provide favorable compressive stresses in the inner region on the DMW to mitigate potential PWSCC; (2) a margin of more than 10 exists between the calculated leak rate from the leakage flaw size and the detection capability of the RCS leakage detection system; (3) a margin of more than 2 exists between the critical flaw size and the leakage flaw size; (4) input parameters (e.g., loadings and crack morphology) are applied consistent with SRP Section 3.6.3; and (5) the methodology is adequate. Therefore, the RCP discharge and suction nozzles with associated DMWs exhibit lBB behavior consistent with the guidance in SRP Section 3.6.3, Revision 1. Pursuant to GDC 4 of Appendix A to 10 CFR Part 50, the NRC staff concludes that the licensee is permitted to continue to exclude consideration of the dynamic effects associated with the postulated rupture of the RCP discharge and suction nozzles from the current licensing basis at DBNPS.
The Commission 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
8.0 REFERENCES
- 1. "Materials Reliability Program: Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs {MRP-169)," Rev. 1, EPRI, Palo Alto, CA, and Structural Integrity Associates, Inc., San Jose, CA: 2008. 1012843.
- 2. "Materials Reliability Program: Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82,182, and 132 Welds (MRP-115)," EPRI, Palo Alto, CA, 2004, 1006696.
B. Allen - 2 Corrected Amendment No. 281 to NPF-3 page 1 and safety evaluation pages 3, 8, 11, 13, 14 and 16 are enclosed. If you or your staff have any questions, please call me at 301-415-3867 Sincerely, IRA!
Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
Amendment No. 281 to NPF-3 cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 RtF RidsRgn3MailCenter Resource RidsNrrDor1LpI3-2 Resource RidsOgcRp Resource RidsNrrDor1Dpr Resource RidsNrrPMMahoney Resource RidsNrrDciCpnb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLATHanis Resource ADAMS Accession No ML100970549 NRR-106 OFFICE NAME LPL3-2/PM MMahoney e 3-2/LA THarris LPL3-2/BC NDiFrancesco for SCampbell DATE 04/9/10 04/8/10 04/9/10 OFFICIAL AGENCY RECORD