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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 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 2024-08-01
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- FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 3081 August 7, 2004 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 for changes and errors to the Emergency Core Cooling System (ECCS) Evaluation Model (EM) used at the Davis-Besse Nuclear Power Station (DBNPS). This report covers the period of January 1, 2003 to December 31, 2003.
If you have any questions or require additional information, please contact Mr. Gregory A. Dunn, Manager, Regulatory Affairs, at (419) 321-8450.
Very truly yours, AWB/s (k
Attachments cc: Region III Administrator DB-1 NRC Senior Resident Inspector DB-1 NRC Senior Project Manager Utility Radiological Safety Board of Ohio 0 al
Docket Number 50-346 License Number NPF-3 Serial Number 3081 Page 1 of 3 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.
EM Description This model is applicable to all Babcock &Wilcox (B&W) designed pressurized water reactors for large and small break LOCA analyses. The NRC approved topical report for this evaluation model was BAW-10192P-A (Reference 1).
The large break loss of coolant accident (LBLOCA) Evaluation Model consists of four computer codes: (1) BAW-10164P-A, RELAP5/MOD2-B&W to compute the system, core, and hot control rod response during blowdown (Reference 2),
(2) BAW-10171P-A, REFLOD3B to calculate the time for refill of the lower plenum and core reflood rate (Reference 3), (3) BAW-10095-A, CONTEMPT to compute the containment pressure response (Reference 4), and (4) BAW-10166P-A, BEACH (RELAP5/MOD2-B&W reflood heat transfer package) to determine the hot pin thermal response during refill and reflood phases (Reference 5 and Reference 6). The small break loss of coolant accident (SBLOCA) Evaluation Model consists of two codes: (1) BAW-10164P-A, RELAP5/MOD2-B&W to compute the system, core, and hot control rod response during the transient and (2) BAW-10095-A, CONTEMPT to compute the containment pressure response, if needed. A NRC-approved fuel code (currently BAW-10162P-A, TACO3
[Reference 7] or BAW-10184P-A, GDTACO [Reference 8]) is used to supply the fuel rod steady-state conditions at the beginning of the small or large break LOCA. These codes are approved for use with M5 cladding via the Safety Evaluation Report (SER) on BAW-10227P-A (Reference 9).
Docket Number 50-346 License Number NPF-3 Serial Number 3081 Page 2 of 3 EM Changes or Errors Change of RELAP5/MOD2-B&W for Mark-B-HTP Fuel The BHTP Critical Heat Flux (CHF) correlation from BAW-10241P (BHTP DNB Correlation Applied with LYNXT, Reference 10) was implemented into the RELAP5/MOD2-B&W code for analysis of Mark-B-HTP fuel. This change was made to support the EM requirement in Section 4.3.4.8 of Volume 1 of BAW-10192P-A (Reference 1), which states that the LOCA analyses will use the same CHF correlation that is used for the fuel pin Departure from Nucleate Boiling (DNB) analyses.
- EM Change - Include BHTP CHF correlation in RELAP5/MOD2-B&W.
- A PCT change is not applicable to non-Mark-B-HTP fuel assemblies because introduction of this correlation does not affect the temperature calculation for those analyses.
- There are no changes to Davis-Besse PCT as a result of changes to RELAP5/MOD2-B&W code for Mark-B-HTP Fuel (CHF Correlation).
EM Application Changes or Errors Reduced High Pressure Iniection (HPI) Flows In response to surveillance tests of the modified HPI pumps, an additional three percent reduction in the HPI flows was analyzed and assessed to determine the impact on the SBLOCA spectrum results. The analyses were performed based on EM RO.6 to allow for a potential Appendix K uprate during Cycle 14 with credit of the Caldon instrumentation (used to measure Feedwater flow). With the reduction in the HPI flow rate, the PCT for the limiting SBLOCA (full area HPI line) was analyzed to be 1504.8 degrees Fahrenheit (F), for an increase of 77.3 F.
The results of the HPI line break analysis were used to evaluate the full LOCA spectrum. It was determined that the full area HPI line break remained limiting.
The analyses and evaluations were performed in Reference 11 and the results reported to FirstEnergy Nuclear Operating Company via Reference 12. Since the analysis resulted in a PCT increase greater than 50 F, this change was reported to the NRC in Reference 13.
The HPI is not directly credited in the LBLOCA PCT analyses.
- Plant Change - Reduced HPl flows for modified HPI pump.
- The SBLOCA PCT was analyzed to be 1504.8 F for this plant change, an increase of 77.3 F.
Docket Number 50-346 License Number NPF-3 Serial Number 3081 Page 3 of 3 References
- 1. AREVA 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. AREVA Topical Report BAW-10164P-A, Rev. 4, "RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis," November 2002.
- 3. AREVA Topical Report BAW-10171P-A, Rev. 3, "REFLOD3B - Model for Multinode Core Reflooding Analysis," December 1995.
- 4. AREVA Topical Report BAW 10095-A, Rev. 1, "CONTEMPT - Computer Program for Predicting Containment Pressure-Temperature Response to a LOCA," April 1978.
- 5. AREVA Topical Report BAW- 10166P, Rev. 5, "BEACH - A Computer Program for Reflood Heat Transfer During LOCA," December 2001.
- 6. Letter dated November 7, 2003 from H. N. Berkow USNRC to J. F. Mallay (Areva), "Issuance of Revised Safety Evaluation for Referencing of Appendices H and I to BAW-10166P-A, "BEACH - Best Estimate Analysis Core Heat Transfer, A Computer Program for Reflood Heat Transfer During LOCA", (TAC No. MC0341), USNRC ADAMS Accession Number ML033140275.
- 7. AREVA Topical Report BAW-10162P-A, Rev. 0, "TACO3 Fuel Pin Thermal Analysis Code," October 1989.
- 8. AREVA Topical Report BAW-10184P-A, Rev. 0, "GDTACO Urania- Gadolinia Fuel Rod Thermal Analysis Code," February 1995.
- 9. AREVA Topical Report BAW-10227P-A, Rev. 1, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," June 2003.
- 10. AREVA Topical Report BAW-10241P, "BHTP DNB Correlation Applied with LYNXT," December 2002.
- 11. AREVA Proprietary Document 32-5004328-03, "DB Mk-B 10K SBLOCA Spectrum", December 10, 2003.
- 12. AREVA Letter FANP-03-3586 dated December 10, 2003, from J. A. Klingenfus (AREVA) to K. S. Zellers (FirstEnergy), "Project Number 4160529, 'Full Double-Ended Guillotine HPI Line Breakl with 4.5% HPI Head Reduction"'.
- 13. Letter to NRC, Serial Number 3017, dated January 5, 2004,
Subject:
Notification of Significant Change of Input to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3)
Docket Number 50-346 License Number NPF-3 Serial Number 3081 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