Letter Sequence Response to RAI |
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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
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R r s t E n ergy N uc l ea r Opera ting C omp a ny Raymo n d A Li eb Vice President, Nuclear December 18, 2012 L-12-438 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No.1 Docket No. 50-346, License No. NPF-3 5501 North State Route 2 Oak Harbor, Ohio 43449 419-321-7676 Fax. 419-321-7582 10 CFR 50.46(a)(3)(ii)
Response to Request for Additional Information on 10 CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models (TAC No. ME8411) By letter dated March 16,2012 (Accession No. ML 12076A237), FirstEnergy Nuclear Operating Company (FENOC) submitted a notification of a significant change and error to the large-break loss-of-coolant accident emergency core cooling model in accordance with Title 10 of the Code of Federal Regulations, Section 50.46(a)(3) for the Davis-Besse Nuclear Power Station, Unit No.1. On November 16,2012, the Nuclear Regulatory Commission (NRC) staff requested additional information regarding this report (Accession No. ML 12310A012).
FENOC's response to the request, as discussed with NRC staff on October 29, 2012, is attached.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, ManagerFleet Licensing, at (330) 315-6810. Raymond A. Lieb
Attachment:
Response to Request for Additional Information on the Notification of Significant Change to the Large-Break Loss-of-Coolant Accident Emergency Core Cooling Model cc: NRC Region III Administrator NRC Resident I nspector Nuclear Reactor Regulat i on Project Manage r Utility Radiological Safety Board Attachment L-12-438 Response to Request for Additional Information on the Notification of Significant Change to the Large-Break Loss-of-Coolant Accident Emergency Core Cooling Model Page 1 of2 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 16, 2012, FirstEnergy Nuclear Operating Company (FENOC), sent a notice reporting a change or error discovered in an evaluation model, or in the application of such a model, that affects the peak cladding temperature (PCT) calculation for Davis-Besse Nuclear Power Station (DBNPS). On November 16, 2012, the NRC requested additional information regarding this notice. The NRC staff's request is presented in bold type, followed by FENOC's response.
- 1. There are two changes to PCT for large-break loss-of-coolant accident (LBLOCA) analysis discussed in the report submitted by the licensee.
The first change is an Evaluation Model (EM) application error in the determination of the end of emergency core cooling system (ECCS) bypass, which resulted in an 80 of decrease in PCT. The second change is an EM modeling change to include the effects of the' upper plenum column weldments, which resulted in an 80 of increase in PCT. Provide the analysis that lead to each change having an 80 of change in PCT. Response Details of the analyses performed by AREVA, the fuel vendor in evaluating the two EM changes, (in non-proprietary report ANP-3180, Revision 000, "177 Fuel-Assembly Plant RAI Responses to a 30-Day 50.46 Report of Significant PCT Change," December 2012) were submitted to the NRC by AREVA letter, "Generic RAI Response to a 30-Day 10 CFR 50.46 Report of Significant PCT Change," on December 6,2012. FENOC has reviewed ANP-3180, Revision 000, and has determined that the conclusions are applicable to DBNPS. 2. 10 CFR 50.46(a)(3)(ii) states: II *** If the change or error is significant, the applicant or licensee shall provide this report within 30 days and include with the report a proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 50.46 requirements
- " The PCT for LBLOCA for DBNPS has changed by an absolute value of 160 OF since the analysis was performed.
Simply reporting the changes and errors in the methodology does not satisfy the intent of the regulation.
Justify not providing a schedule for reanalysis or taking other action to show compliance with 10 CFR 50.46 Attachment L-12-438 Page 2 of2 Response In accordance with 10 CFR 50.46(a)(3)(ii), on May 27,2011 (Accession No. ML 111510642), FENOC submitted a Report of Changes or Errors for the current PCT for a large-break LOCA at DBNPS as being 2,119°F. By letter dated February 13,2012 (Accession No. ML 120440609)
FENOC discussed the basis for this value. This was the last reported value prior to the identification of these errors. The AREVA report referenced in the response to Question 1 provides additional details regarding the analytical bases for the PCT error estimates, which were based upon explicit RELAP5/Mod2-B&W code runs for a Babcock & Wilcox (B&W)-designed nuclear steam supply systems (NSSS). The error that was corrected in the evaluation models was specific to the determination of the end of emergency core cooling system (ECCS) bypass. A separate change to the ECCS evaluation model was made based on the effects of the upper plenum column weldments.
As evidenced by the information provided by AREVA's response to Question 1, both of the EM items have been analyzed in detail. Furthermore, the impact on the ECCS evaluation model does not result in any challenge to the 10 CFR 50.46(b) acceptance criteria.
As the individual items have been analyzed and there are no other known errors or changes to be evaluated at this time, the overall evaluation model is considered acceptable.
In summary, the responses to the NRC staff requests establish the following:
- The error-adjusted PCT for a large-break LOCA at DBNPS remains below the 10 CFR 50.46(b) acceptance criteria and is considered to be adequate.
- The SBLOCA analyses are not affected by the reported ECCS evaluation model errors.
- The AREVA response referenced in Question 1 provides additional information regarding the nature of the PCT change evaluations, which are supported by explicit analyses using the B&W plant ECCS evaluation model. Based on the above, there are no adverse impacts to safety. Revision of the EM or design basis analysis-of-record for DBNPS is not warranted.