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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:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 2023-08-07
[Table view] Category:Technical
MONTHYEARL-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. ML13008A0612012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-By Checklists, Sheet 21 of 139 Through End L-15-328, Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 72012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 7 ML15299A1502012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 6 of 7 ML15299A1492012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 5 of 7 ML15299A1482012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 4 of 7 ML15299A1472012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 3 of 7 ML15299A1462012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 2 of 7 ML15299A1442012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 1 of 7 ML12209A2602012-07-26026 July 2012 Attachment 31, Fauske & Associates, Inc. Technical Bulletin No. 1295-1, BWR MSIV Leakage Assessment: NUREG-1465 Vs. MAAP 4.0.2 ML1017400422010-06-0404 June 2010 0800368.407, Rev. 0, Summary of Design and Analysis of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigati L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds 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 ML11301A2222008-12-0101 December 2008 Reference: Combined Heat and Power Effective Energy Solutions for a Sustainable Future ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 L-08-105, Reactor Head Inspection Report2008-04-11011 April 2008 Reactor Head Inspection Report L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse2008-01-27027 January 2008 Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse ML0726105652007-09-17017 September 2007 Confirmatory Order, 2007 Independent Assessment of Corrective Action Program (FENOC) ML0708602802007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity ML0708602762007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus ML0708602712007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3 ML0708602682007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues ML0708602612007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking ML0708602562007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 4. the Davis-Besse March 2002 Event ML0708602532007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background 2023-01-10
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FENOC "FEN % 5501 North State Route 2 FirstEnergy Nuclear OperatingCompany Oak Harbor,Ohio 43449 Lew W. Myers 419-321-7599 Chief Operating Officer Fax 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial 2824 November 18, 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Regulatory Commitment Change Summary Report (May 18, 2000 - May 18, 2002)
Ladies and Gentlemen:
The FirstEnergy Nuclear Operating Company (FENOC) hereby submits the attached Regulatory Commitment Change Summary Report for the Davis-Besse Nuclear Power Station, Unit Number 1 (DBNPS), pursuant to the Nuclear Energy Institute (NEI) document, "Guideline for Managing NRC Commitments," Revision 2, dated December 19, 1995. DBNPS adopted the above guideline with a revision to the Commitment Management procedure effective April 1, 1996.
The DBNPS commitment changes identified between the dates of May 18, 2000 and May 18, 2002 are included in Attachment 1 of this report. This report includes a description of the identified commitments, a summary of the changes made to the commitments, and a brief statement describing the basis for the change. The DBNPS has reviewed and implemented the commitment changes in accordance with the NEI document, "Guideline for Managing NRC Commitments." Per this guideline, DBNPS has determined that the submittal of this report is the only required notification regarding changes to commitments listed in the attached summary.
Also included in this report are six commitment changes recently identified that should have been included in the Regulatory Commitment Change Summary Report (Serial 2575) submitted on November 20, 1998. They are summarized in Attachment 2 to this report.
If you have any further questions concerning this matter, please contact Mr. Patrick McCloskey, Manager Regulatory Affairs at (419) 321-8450.
Sincerely yours, RJS/bw *-----------*
Attachments cc: J. B. Hopkins, DB-1 NRC/NRR Senior Project Manager J. E. Dyer, Regional Administrator, USNRC Region III C. S. Thomas, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board SAOc
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 1 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 001256 Door 400 (Spent Fuel Pool EVS This commitment is closed. The This requirement is discussed as LER 82-057, Rev 1 negative pressure boundary) was "Basic Security Procedure" part of training received for 07/06/1984 found not completely closed and signature page stating station Protected Area Access. This latched due to personnel error. personnel are responsible for commitment is unnecessary Corrective Action was to have all ensuring plant doors close behind based on the quality of this sign a page in a "Basic Security them has been superceded by training and the maturity of the Procedures" document stating other program requirements and Access Authorization Program.
they are responsible for ensuring can be cancelled.
plant doors close behind them.
001275 Procedures are in place to ensure Procedures specify Revised procedural guidance to LER 83-012 Rev. 2 that if one ECCS Room Cooler (or isolating/draining a single ECCS incorporate licensing basis 05/05/83 one ECCS Cooler in each room) is Room Cooler for a given ECCS assumptions of License isolated, that the Service Water Room will render an associated Amendment 242, which increased temperature is less than or equal Train of ECCS components the maximum Service Water to 75 degrees Fahrenheit. (DH/LPI/HPI & CTMT Spray) temperature from 85 degrees inoperable unless Service Water Fahrenheit to 90 degrees temperature is below specified Fahrenheit.
values and other specified conditions are acceptable.
003558 Prohibit suspension of a work Commitment closed. The site procedures and the work Log 1-0401 order. order software do not provide or 01/06/1984 allow an option to suspend a work order.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 2 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 004239 Maintain PM activities for Delete PM activities requiring the A modification removed the Serial 1-1033 applicable Agastat relays with replacement of the Agastat relays Agastat relays for electrical 01/28/1994 appropriate replacement for electrical schemes AC108, schemes AC108, AC113, AD108 frequency. AC113, ADi08 & AD113. & AD1 13 from the plant. Since the relays have been removed, the PMs are no longer applicable.
008625 Maintain a list of qualified design Commitment closed. A formal training program is now LER 88-008 reviewers. Maintenance of a separate list of in effect to ensure engineers 04/08/1988 qualified reviewers is not assigned design review administratively necessary. responsibility meet job specific qualifications. It is the responsibility of the Engineering Supervisor to ensure the assigned reviewer is qualified for the task assigned.
012223 Verify the CAC fans are Revise commitment to permit Permit alternate means of SERIAL 1-0645 discharging air in slow speed to alternate means of verifying verifying airflow if plenum 08/14/1986 show it is running in the proper airflow (e.g., plenum pressure, pressure transmitter fails during direction. Air flow is determined motor current, differential power operations. Subsequent by monitoring CAC plenum temperatures, or other methods). maintenance on the failed plenum pressure. pressure transmitter would require an "at power" containment entry in a high radiation area. This is unnecessary as alternate means exist to verify the CACs are operating properly.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 3 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 013608 Changes to drawings contained in Commitment closed. Commitment was initiated due to IR 84-015 (Log 1-0490) the FSAR should be subject to oversight by personnel in early 01/14/1985 10CFR50.59 evaluation 1980's. Consideration that an evaluation is required for changes to USAR Drawings is now implicit in the fact that the drawings are part of the USAR.
013660/013661 Category A valve leak rate test Commitments have been The Third Ten Year ASME IST Serial 1-0526 program meets the requirements superseded by new requirements Program follows the 1995 Edition, 5/17/1985 of ASME Section X1, IWV-3426 and, therefore, are closed. 1996 Addenda of the OM Code for and IWV-3427. valve leak testing.
013663 Provide procedural requirement Commitment closed. Standardization and improved IR 87-004 (Log 1-1600) that a copy of all 10CFR50.59 efficiency of work process.
05/08/1987 safety evaluations be provided to A web page has been established Nuclear Licensing Manager for for electronic filing and retrieval of incorporation into annual report to 50.59 evaluations from which RA NRC. is able to retrieve copies of all required safety evaluations.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 4 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 013771 PM program provides: Changes to the PM approval Changes in the review/approval Serial 1231 New, revised or deleted PM items levels are as follows: level is based upon past 01/03/1986 (PMAs) are approved by New, revised or deleted PM items performance of the PM program.
designated engineer, maintenance - designated engineer or Deferrals for the last 2 years have planner or supervisor work control; maintenance planner or PM been less than the maximum goal deferrals for PM items (PMDs) Coordinator (EQRL Engineer); and no deferrals past the grace which do not exceed 125% deferrals for PM items which do period (>125%) have been performance window are not exceed 125% performance submitted since 1999.
approved by supervisor work window - N/A; deferrals for PM control or discipline maintenance items which allow the item to superintendent; deferrals for PM exceed the 125% performance items which allow the item to window - plant operations exceed the 125% performance manager or discipline window are approved by plant maintenance superintendent.
operations manager or plant maintenance manager.
013930 Perform calibration of PZR code The pressure gauge used to Conformance with current Code IR 88-006 (Log 1-1783) safety valves and PORV under hot determine the lift setpoint will meet requirements. The old Code gave 04/20/1988 conditions. Pressure gauge used current OMa Code or ASME Xl no tolerance. The new Code to determine lift setpoint to have requirements used by DBNPS. gives a tolerance that is less an accuracy of plus or minus 0.1% stringent but adequate to ensure and a corresponding error of 5 psi. that testing requirements are met.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 5 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 014906 The Emergency Planning Activity Procedure specifies activities that To permit evaluation and tracking Serial 1-0501 Scheduling System will be used to will be tracked in the Emergency of Emergency Preparedness 02/28/1985 identify and maintain Planning Activity Scheduling related "conditions adverse to commitments, required activities, System and specifies activities quality" in the DBNPS Condition routing activities and correction of involving corrective actions to be Report system similar to other action items. tracked in the DBNPS corrective identified conditions adverse to action program. quality.
015078 Main Steam Line Room smoke Commitment closed. A modification abandoned these Serial 1685 detectors are verified for Main Steam line Room smoke 07/31/1989 operability every 18 months and detectors.
when the unit has been shutdown for maintenance.
015085 The Emergency Planning Activity Procedure specifies activities that To permit evaluation and tracking Serial 1-0501 Scheduling System will be used to will be tracked in the Emergency of Emergency Preparedness 02/28/1985 track all Emergency Preparedness Planning Activity Scheduling related "conditions adverse to activities including NRC and INPO System and specifies activities quality" in the DBNPS Condition commitments, drill and exercise involving corrective actions to be Report system similar to other critique items, required tracked in the DBNPS corrective identified conditions adverse to performance tests, required action program. quality.
training, and Quality Assurance audit finding reports.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 6 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 015277 Sample the Diesel Fire Pump Eliminated monthly sampling of Actions changed to be in Serial 1685 lubricating oil monthly to meet the the lubricating oil of the Diesel Fire compliance with standard NFPA 7/31/1989 intent of standard NFPA 13A Pump. Oil is now replaced every 13A 1982, 2-4.1.6.
1981, 2-4.1.6. The oil is changed 12 months.
at 18-month intervals instead of annually as specified in the standard.
015554/015555 Control Room Emergency CREVS Condenser Units are The change to the frequency is a GL 89-013 (Log 2997) Ventilation System Condenser inspected and cleaned (if precautionary measure to ensure 07/18/89 Units are cleaned at least once required) at least once every 18 early detection/elimination of a every 36 months. months. potential bio-fouling condition.
Although bio-fouling has not been historically found in the CREVS system, the frequency should be increased as a precautionary measure to ensure early detection/elimination.
015555 Test the Decay Heat Cooler Remove testing of the Decay Heat The CCW system does not obtain GL 89-013 (Log 2997) performance every 5 years. Coolers from the GL 89-013 make up from the SW system and 07/18/1989 Program. chemistry controls are routinely well maintained. Heat transfer testing and visual inspections of CCW heat exchangers in the last 10 years have not identified any conditions of degraded heat transfer.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 7 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 015555 Conduct CCW Heat Exchanger CCW Heat Exchanger testing now Follow up inspections have not GL 89-013 (Log 2997) performance testing once per year done one each year: each heat identified any fouling in recent 07/18/1989 for the GL 89-013 program. exchanger is tested once every 3 years. The reason for not meeting years. previous tests was found to be poor test design which has been improved.
015921 Monitor MU Pump performance to The alert level at which action was A calculation provided the Serial 1836 ensure that feed and bleed required has been deleted. The appropriate value to be used in 09/18/1990 capability is maintained by surveillance procedure contains a the surveillance test.
requiring action at an alert level set value at which action is when the MU Pump appears to be required.
degrading.
016667 Procedures include preoperational The commitment now only applies The Third Ten-year Interval IST LER 92-003 checks of surveillance to two valves SW 1424 and Program has on-line testing 4/22/1992 requirements for their associated SW 1429. requirements for SW 1424 and IST valves. SW 1429. The other valves previously in the commitment are tested only when the plant is shutdown per the Third Ten-Year Interval IST Program.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 8 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 017419 Valves SW232, SW233, SW236 Commitment closed. The function of these valves has IR 93-016 (Log 1-2963) and SW234 (SW to CCW cross been reviewed and reclassified 12/29/1993 connect valves) are exercised and now are considered to fall once each cycle to ensure valve under the ASME Code reliability. requirements. The ASME Code requires these valves be part of the IST Program and, therefore, are included in the current Second Interval IST Program.
017955 Annual PM activities perform PM frequency changed from After five years of monitoring with IR 94-017-02 (Log 1-3550) electronic characteristic and annual to every two years. no evidence of water intrusion the 02/13/1995 diagnostic (ECAD) testing on PM periodicity has been re cables known to be in a wet assessed. The original interval environment. was a conservative frequency.
018252 Breakers required to connect the Breakers will be verified to be in The fuse blocks were changed out Amendment 206 (Log 4795) SBODG to the essential bus the position required for the to due to the wear and 02/26/1996 associated with the EDG removed existing operational mode and unavailability of the old fuse from service will be verified to be plant conditions, with close and blocks. The new fuse blocks do in the position required for the trip fuses installed by a visual not allow direct sight of the existing operational mode and verification that the fuse block is installed fuse.
plant conditions, with close and closed without any clearance tags.
trip fuses installed through a breaker line-up check.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 9 of 9 Commitment Commitment Change Reason for Change Number / Source / Date Description 018574 Maintain Control Room Pressure Maximum permissible opening for Revised Calculation determined LER 96-007 Boundary openings less than 3 the Control Room positive the maximum permissible opening 11/14/1996 square inches to ensure no Pressure Boundary is 7.5 square for the Control Room Pressure unattended openings exist inches. Boundary to be 7.5 square inches between the CREVS fan and the with the Control Room Equipment filter housing. Fan running.
018789 The Start-up Transformers 01 & Commitment closed. A modification installed a LER 97-010 02 Deluge Tests periodically "permissive interlock" which 06/03/1997 check the temperature sensors to requires the start-up transformer ensure the setpoint of the sensors to be de-energized before the has not drifted outside acceptable deluge system will initiate.
values. This eliminates spurious Additionally, the detector actuation transformer fire protection deluge is an "alarm only" function and a system actuations. low setpoint will no longer result in an automatic actuation of the deluge system, eliminating the potential for a spurious deluge actuation.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 1 of 2 Commitment Commitment Change Reason for Change Number / Source / Date Description 004851 Administrative controls preclude Lanyards are no longer required to The use of lanyards was an over GL 85-002, Serial 1161 the introduction of foreign objects for tools used within the Steam commitment in response to the 4/17/1985 into the Steam Generators during Generators. Generic Letter requirements, and maintenance. Accountability of is not practical in all cases. Tool tools and equipment is maintained accountability is still maintained by entry and exit logs. All tools through the use of entry and exit used are attached to lanyards. logs.
005641 Polyethylene filtered bottles are The use of polyethylene filter It is not the best practice for GL 87-012, Serial 1423 used to vent the RCS to bottles is optional when venting maintaining dose As Low As 7/9/1987 containment to trap moisture and the RCS. Reasonable Achievable (ALARA) contaminants. to require polyethylene filter bottles at all vent points at all times.
013548/013563 Maintain maintenance procedure Deleted requirement to inspect Bulletin 82-002 did not require the Bulletin 82-002, IR 84-028-07 to inspect threaded fasteners threaded fasteners via magnetic use of non-destructive 1/18/1985 during disassembly, inspection, particle non-destructive examination methods (such as repair and re-assembly of the examination methods. Procedure magnetic particle examination) to Reactor Coolant Pump. still performs visual inspection of inspect threaded fasteners.
Fasteners are inspected visually fasteners.
and by utilizing magnetic particle non-destructive examination methods.
Docket Number 50-346 DAVIS-BESSE NUCLEAR POWER STATION License Number NPF-3 COMMITMENT CHANGE SUMMAY REPORT Serial Number 2824 MAY, 2000 - MAY, 2002 Page 2 of 2 Commitment Commitment Change Reason for Change Number / Source / Date Description 013804 Maintain maintenance procedure Commitment closed. The Turbine Bypass Valves for LER 88-028 to ensure proper setup of the which this commitment applied 1/16/1989 positioner and travel stop for the were replaced with a completely Turbine Bypass Valves. different style valve and actuator.
014530 Maintain calibration procedure to Commitment closed. The Turbine Bypass Valves for IR 87-025, Log 1-1678 clearly establish the testing which this commitment applied 10/1/1987 connections, provide for tighter were replaced with a completely alignment criteria, and verify different style valve and actuator.
mechanical and electrical limits of the Turbine Bypass Valves.
Docket Number 50-346 License Number NPF-3 Serial Number 2824 Page 1 of 1 List of Abbreviations Used ASME American Society of Mechanical Engineers CAC Containment Air Cooler CCW Component Cooling Water CREVS Control Room Emergency Ventilation System DBNPS Davis-Besse Nuclear Power Station EDG Emergency Diesel Generator EVS Emergency Ventilation System GL Nuclear Regulatory Commission Generic Letter IR Nuclear Regulatory Commission Inspection Report IST Inservice Testing LER Licensee Event Report MU Make-Up NRC Nuclear Regulatory Commission PM Preventive Maintenance PORV Pressurizer Operated Relief Valves PZR Pressurizer RCS Reactor Coolant System SBODG Station Blackout Diesel Generator SERIAL Letter from Davis-Besse Nuclear Power Station to Nuclear Regulatory Commission SW Service Water USAR Updated Safety Analysis Report