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Category:Annual Report
MONTHYEARL-20-033, Submittal of Annual Financial Report2020-03-23023 March 2020 Submittal of Annual Financial Report ML14140A2152014-05-15015 May 2014 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for 2013 ML0715003912007-05-25025 May 2007 Report of Changes to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3) for the Period of January 1, 2006 to December 31, 2006 L-06-065, 2005 Annual Report for Firstenergy Corp; Retrospective Premium Guarantee2006-04-0606 April 2006 2005 Annual Report for Firstenergy Corp; Retrospective Premium Guarantee L-05-067, Letter Transmitting Firstenergy Corp. 2004 Annual Report2005-04-0808 April 2005 Letter Transmitting Firstenergy Corp. 2004 Annual Report ML0424003822004-08-0707 August 2004 Annual Report of Changes to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3) ML0412601252004-04-29029 April 2004 2003 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report L-04-037, Letter Forwarding 2003 Firstenergy Corp. Annual Report2004-04-12012 April 2004 Letter Forwarding 2003 Firstenergy Corp. Annual Report ML0324708282003-08-29029 August 2003 Annual Report of Changes to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3) L-03-045, Firstenergy Corporation Retrospective Premium Guarantee2003-04-0404 April 2003 Firstenergy Corporation Retrospective Premium Guarantee ML0310007252003-04-0404 April 2003 Retrospective Premium Guarantee, Annual Report ML0222101182002-08-0606 August 2002 Annual Report of Changes to Emergency Core Cooling System Evaluation Model in Accordance with 10CFR50.46(a)(3) L-02-041, Annual Financial Reports & Certified Financial Statements for Perry Nuclear Power Plant, Davis-Besse Nuclear Power Station & Beaver Valley Power Station2002-04-24024 April 2002 Annual Financial Reports & Certified Financial Statements for Perry Nuclear Power Plant, Davis-Besse Nuclear Power Station & Beaver Valley Power Station L-02-044, 2001 Firstenergy Corp. Annual Report Completing Requirements for Retrospective Premimum Guarantee2002-04-16016 April 2002 2001 Firstenergy Corp. Annual Report Completing Requirements for Retrospective Premimum Guarantee L-02-029, Property Insurance Coverage - 2001 Annual Notification for Perry, Davis-Besse & Beaver Valley2002-03-21021 March 2002 Property Insurance Coverage - 2001 Annual Notification for Perry, Davis-Besse & Beaver Valley ML0036962172000-03-17017 March 2000 Letter Forwarding Documents as Evidence of Licensee Guarantee of the Retrospective Premiums Which May Served Against the Davis-Besse, Unit 1, Perry, Unit 1, and Beaver Valley, Units 1 and 2 ML0037089641998-04-20020 April 1998 Annual Financial Reports and Certified Financial Statements for the Perry Nuclear Power Plant (Docket Number 50-440) and the Davis-Besse Nuclear Power Station (Docket Number 50-346) 2020-03-23
[Table view] Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23160A2342023-06-13013 June 2023 Confirmation of Initial License Examination L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models IR 05000346/20235012023-06-13013 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501 L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection IR 05000346/20230102023-05-0909 May 2023 Commercial Grade Dedication Inspection Report 05000346/2023010 ML23123A1272023-05-0303 May 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station IR 05000346/20230012023-05-0101 May 2023 Integrated Inspection Report 05000346/2023001 and 07200014/2022001 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 ML23111A1972023-04-26026 April 2023 Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station ML23114A1062023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23096A1382023-04-11011 April 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage ML23066A2892023-03-14014 March 2023 Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement ML23066A2592023-03-14014 March 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 2024-02-02
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Davis-Besse Nuclear Power Station irstEn 5501 North State Route 2 Oak Harbor,Ohio 43449-9760 Docket Number 50-346 License Number NPF-3 Serial Number 2801 August 6, 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Annual Report of Changes to the Emergency Core Cooling System Evaluation Model In Accordance With 10 CFR 50.46(a)(3)
Ladies and Gentlemen:
In accordance with 10 CFR 50.46(a)(3), the FirstEnergy Nuclear Operating Company (FENOC) herewith submits the attached annual report of the Emergency Core Cooling System (ECCS) Evaluation Model (EM) used at the Davis-Besse Nuclear Power Station (DBNPS). No new changes or errors to the EM occurred for the period of January 1, 2001 to December 31, 2001.
If you have any questions or require additional information, please contact Mr. Patrick J. McCloskey, Manager, Regulatory Affairs, at (419) 321-8450.
Very truly yours,
.Mers w -4 Vice President - Nuclear Davis-Besse Nuclear Power Station AWB/s Attachments
Docket Number 50-346 License Number NPF-3 Serial Number 2801 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8450) at Davis-Besse of any questions regarding this document or associated regulatory commitments.
COMMITMENTS DUE DATE None N/A
Docket Number 50-346 License Number NPF-3 Serial Number 2801 Page 1 of 4 Annual Report of Changes to the 10 CFR 50.46 Emergency Core Cooling System Evaluation Model for the Davis-Besse Nuclear Power Station 10 CFR 50.46 (a)(3) states that each holder of an operating license shall report to the Nuclear Regulatory Commission (NRC) at least annually each change or error in an acceptable Emergency Core Cooling System (ECCS) Evaluation Model (EM) or in the application of such a model that affects the Peak Cladding Temperature (PCT) calculation.
For the period January 1, 2001 through December 31, 2001, no significant changes or errors (which resulted in a PCT difference greater than 50 degrees Fahrenheit (F)) were identified in the RELAP5 based EM that was used for licensing analysis for the Davis-Besse Nuclear Power Station (DBNPS). Specifically, no significant changes or errors were discovered in the RELAP5/MOD2-B&W-based Babcock & Wilcox Nuclear Technologies (BWNT) Loss of Coolant Accident (LOCA) EM, BAW-10192P-A, Revision 0 (Reference 1) that covers both Large Break (LB) LOCA and Small Break (SB) LOCA including applications with M5TM fuel cladding as described in BAW-10227P-A (Reference 2). Also, no input errors were detected that changed the results of the most limiting SBLOCA or LBLOCA analysis.
For the period January 1, 2001 to December 31, 2001 no new changes or errors are reported by the DBNPS. However, previously reported items that were included in the NSSS vendor annual report (Reference 3) are included to maintain consistency with the NSSS vendor letter.
RELAP5/MOD2-B&W Once Through Steam Generator Large and Small Break LOCA Evaluation Model This model is applicable to all B&W designed pressurized water reactors for large and small break LOCA analyses. The NRC approved topical report for this evaluation model is BAW 10192P-A Revision 0 (Reference 1).
The large break LOCA Evaluation Model consists of four computer codes: (1) RELAP5/MOD2 B&W to compute the system, core, and hot rod response during blowdown, (2) REFLOD3B to calculate the time for refill of the lower plenum and core reflood rate, (3) CONTEMPT to compute the containment pressure response, and (4) BEACH (RELAP5/MOD2-B&W reflood heat transfer package) to determine the hot pin thermal response during refill and reflood phases.
The small break LOCA Evaluation Model consists of two codes: (1) RELAP5/MOD2-B&W to compute the system, core, and hot rod response during the transient and (2) CONTEMPT to compute the containment pressure response, if needed. An NRC-approved fuel code (currently TACO3) is used to supply the fuel rod steady-state conditions at the beginning of the small or large break LOCA.
Docket Number 50-346 License Number NPF-3 Serial Number 2801 Page 2 of 4 Correction of RCP Two-Phase Degradation Model for SBLOCA The NRC-approved SBLOCA EM (Volume II of Reference 1) prescribes that the two-phase RELAP5 head difference and degradation multipliers, derived from the semi-scale pump tests, be used with the reactor coolant pump (RCP) performance curves. Examination of the semi-scale pump degradation curves, which are based upon tests run at relatively low pressures, indicate that the RELAP5 model can over-predict the amount of head degradation during the first several minutes of a SBLOCA transient with continued RCP operation (as analyzed in resolution of Preliminary Safety Concern (PSC) 2-00). Comparison of the RELAP5 curves to representative data, specifically the CE 1/5-scale steam-water tests (which were run at higher pressures) confirm that the RELAP5 model over-predicts pump head degradation during two-phase flow early in the event. Since less pump degradation results in additional RCS liquid loss that leads to more extensive core uncovering and higher PCTs, the approved RELAP5 model cannot be judged to be conservative for application to continued RCP operation during a SBLOCA. When a bounding pump performance curve (the lower bound "M3-modified" curves in the approved large break LOCA model) is modeled, the predicted consequences are much more severe.
Therefore, the SBLOCA EM must be corrected to specify that the selection of a RCP two-phase degradation model in future SBLOCA analyses must be justified by sensitivity studies. This approach, which is similar to that used for LBLOCA applications, performs or makes reference to applicable studies that determined which RCP degradation model is conservative for application to plant-specific SBLOCA analyses.
RCP degradation model sensitivity studies were performed to resolve PSC 2-00 with RCP trip at two minutes after loss of subcooling margin. It was concluded from these analysis that the consequences for the Core Flood Tank (CFT) line break are most influenced by this change in degradation. CFT line break sensitivity studies confirmed that the M3-modified curve produces the most conservative results.
For the resolution of this issue at the DBNPS, the large SBLOCAs were analyzed with manual RCP trip at 2 minutes following Loss of Sub-Cooling Margin (Reference 5). The larger cold leg pump discharge breaks predicted more severe consequences than the case with loss of offsite power, however they did not challenge the limiting SBLOCA PCT of 1428 degrees F. The cases were non-limiting compared to other B&W designed plants because the DBNPS utilizes two, high-volume/low-head, high pressure injection (HPI) pumps that each have an equivalent flow capacity of two of the HPI pumps in operation at the other B&W units. Therefore, the PCT change for PSC 2-00 is 0 degrees F.
BEACH Initial Cladding Temperature Range This item was previously reported to the NRC (Reference 4), and is being resolved by a revision to the BEACH topical report (Reference 6) that was submitted to the NRC in December of 2001.
The revision (Reference 7) seeks to extend ranges on the Safety Evaluation Report (SER) restrictions currently in place on the use of BEACH.
Docket Number 50-346 License Number NPF-3 Serial Number 2801 Page 3 of 4 Appendix H was added to the BEACH topical to extend the limitation on the cladding temperature at the onset of reflood. The BEACH SER restriction on Revision 2 limited the cladding temperature to between 950 and 1640 F. All of the demonstration cases presented in the BWNT LOCA EM (Reference 1) and subsequently approved by the NRC had cladding temperatures that exceeded this range. Framatome ANP completed an additional benchmark to assure that the code application could be extended to higher cladding temperatures. This benchmark (Full Length Emergency Core Cooling Heat Transfer - Separate Effects Tests And System Effects Tests Test 34420) provides additional confirmation that the mechanistic modeling of BEACH is adequate and acceptable for reflood heat transfer prediction for plant LOCA application temperatures to 2045 degrees F. This material was provided to the DBNPS for 10 CFR 50.46 reporting for calendar year 1999. After the NRC was informed that the BWNT LOCA EM demonstration cases were outside of this initial temperature range, they stated that this was an error and they requested that a formal revision to the BEACH code topical report be prepared and submitted for review and approval (Reference 7). The extension of the SER restriction on the initial cladding temperatures effectively corrects all application analyses that may have had temperatures outside of the initially approved range.
The PCT change for increasing the acceptable range of initial cladding temperatures in BEACH analyses is 0 degrees F for the DBNPS because no alteration of the code results or formulation was required.
Docket Number 50-346 License Number NPF-3 Serial Number 2801 Page 4 of 4 References
- 1. FTI Topical Report BAW-10192P-A, Rev. 0 "BWNT LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Once-Through Steam Generator Plants," June 1998.
- 2. FTI Topical Report BAW-10227P-A, Rev. 0, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," February 2000.
- 3. Letter to USNRC, "2001 - Annual Reporting of Changes and Errors in ECCS Evaluation Models," Framatome ANP NRC:02:012, February 28, 2002.
- 4. Letter to USNRC, "Annual Report of Changes to the Emergency Core Cooling System Evaluation Model in accordance with 10 CFR 50.46(a)(3)(ii)," Davis-Besse Serial Number 2716, July 5, 2001.
- 5. FRA-ANP Document 51-5009856-00, "Summary of PSC 2-00 Analyses," 4/13/01
- 6. FII Topical Report BAW-10166PA-04. "BEACH - Best Estimate Analysis Core Heat Transfer; A Computer Program for Reflood Heat Transfer During LOCA," February 1996.
- 7. FfI Topical Report BAW-10166P-05, "BEACH - Best Estimate Analysis Core Heat Transfer; A Computer Program for Reflood Heat Transfer During LOCA," December, 2001.