|
|---|
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
[Table view] |
Text
- 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
