Letter Sequence Supplement |
|---|
|
|
MONTHYEARL-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.2009-04-15015 April 2009
License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.
Project stage: Request
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption From.2009-12-18018 December 2009
Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption From.
Project stage: Supplement
ML1019403932010-07-14014 July 2010
Request for Additional Information Regarding Davis-Besse License Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves
Project stage: RAI
L-10-243, Response to a Request for Additional Information Related to a License Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements..2010-08-26026 August 2010
Response to a Request for Additional Information Related to a License Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements..
Project stage: Response to RAI
L-10-278, Supplemental Information Related to a Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50, App. G2010-10-0808 October 2010
Supplemental Information Related to a Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50, App. G
Project stage: Supplement
ML1030602132010-12-14014 December 2010
Exemption from the Requirements of 10 CFR Part 50.61 and 10 CFR Part 50, Appendix G
Project stage: Approval
ML1030602082010-12-14014 December 2010
Exemption from the Requirements of 10 CFR Part 50.61 and 10 CFR Part 50, Appendix G Letter
Project stage: Approval
NRC-2010-0378, Exemption from the Requirements of 10 CFR Part 50.61 and 10 CFR Part 50, Appendix G2010-12-14014 December 2010
Exemption from the Requirements of 10 CFR Part 50.61 and 10 CFR Part 50, Appendix G
Project stage: Approval
ML1036101482011-01-28028 January 2011
Issuance of Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of the Reactor Coolant System Pressure-Temperature Curves
Project stage: Approval
L-11-085, Regarding the Submittal of the Unapproved Pressure and Temperature Limits Report2011-03-0707 March 2011
Regarding the Submittal of the Unapproved Pressure and Temperature Limits Report
Project stage: Other
ML1104604852011-03-17017 March 2011
Correction Letter for License Amendment No. 282 Regarding Request to Incorporate the Use of Alternative Methodologies for the Development of Reactor Vessel pressure-temperature Limit Curves
Project stage: Other
2010-07-14
[Table View] |
|
|---|
Category:Letter type:L
MONTHYEARL-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
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
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
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
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
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
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
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
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-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
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
L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023
Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002
L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023
CFR 50.55a Request RP-5 Regarding Inservice Pump Testing
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023
Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
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-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022
Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)
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-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022
Occupational Radiation Exposure Report for Year 2021 - Correction
L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022
Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022
Submittal of Evacuation Time Estimates
L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022
Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022
Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan
L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022
Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report
L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022
2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022
Post Accident Monitoring Report
L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022
Readiness for NRC Supplemental Inspection Required for a White Finding
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022
Withdrawal of Proposed Inservice Inspection Alternative RR-A2
L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022
Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage
L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022
Report of Facility Changes, Tests, and Experiments
L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022
Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021
L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022
Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022
Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022
Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding
L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022
Occupational Radiation Exposure Report for Year 2021
L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022
Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage
L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022
Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3
L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022
Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022
Ile Post Exam Letter L-22-061
L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022
Retrospective Premium Guarantee
L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022
Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2
L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022
Emergency Plan Amendment Request
L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021
Response to NRC Inspection Report 05000346/2021091, EA-21-176
2023-09-12
[Table view] |
Text
FENOC -" %
Davis-Besse Nuclear Power Station 5501 N. State Route 2 FirstEnergyNuclear OperatingCompany Oak Harbor,Ohio 43449 October 8, 2010 L-1 0-278 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Supplemental Information Related to a Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50, Appendix G (TAC NOS. MEl 127 AND MEl 128)
By letter dated April 15, 2009 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML091130228], as supplemented by letter dated December 18, 2009 (ADAMS Accession No. ML093570103), the FirstEnergy Nuclear Operating Company (FENOC) submitted to the Nuclear Regulatory Commission (NRC) a license amendment request and, an exemption request for the Davis-Besse Nuclear Power Station (DBNPS). The proposed amendment would incorporate the use of alternate methodologies for the development of the reactor pressure vessel pressure-temperature (P-T) limit curves into the DBNPS Technical Specifications.
The proposed exemption would exempt DBNPS from certain requirements contained in 10 CFR 50.61 and 10 CFR Part 50, Appendix G.
By letter dated July 14, 2010 (ADAMS Accession No. ML101940393), the NRC staff requested additional information (RAI) on the proposed amendment to complete its review. FENOC letter dated August 26, 2010 provided the response to the RAI.
On September 3, 2010, a teleconference was held between the FENOC and NRC staffs to discuss the RAI response. During the teleconference clarifications of the RAI responses and the December 18, 2009 submittal were discussed, and are provided in the attachment.
tAN01
Davis-Besse Nuclear Power Station L-1 0-278 Page 2 of 2 There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at (330) 761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October_, 2010.
Sincerely, Kendall W. Byrd Director, Site Performance Improvement
Attachment:
Supplemental Response To Request For Additional Information cc: NRC Region III Administrator NRC Project Manager NRC Resident Inspector Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment L-10-278 Supplemental Response To Request For Additional Information Page 1 of 3 On September 3, 2010, a teleconference was conducted between the FirstEnergy Nuclear Operating Company (FENOC) and the Nuclear Regulatory Commission (NRC) staffs to discuss a Request for Additional Information (RAI) submitted by FENOC on August 26, 2010. During the teleconference, clarifications to the RAI responses and the associated license amendment request dated December 18, 2009 were discussed. The NRC staff questions are in bold, followed by the FENOC responses.
NRC Staff Question 1 The response to Question #3 of the RAI refers to a 28.770 F temperature differential between the reactor coolant and the limiting location in the reactor vessel wall. Was this temperature differential based on a 50 0 F/hour step change heatup or a 75 0F/hour step change heatup?
Response
The temperature differential was controlled more by the heat transfer characteristics of the fluid and metal than the heatup rate, and was essentially the same for both the 50 degrees Fahrenheit (°F)/hour step change heatup and the 75 0F/hour step change heatup.
NRC Staff Question 2 What is the basis for the margin term of 4.570 F added to the temperature differential between the reactor coolant and limiting (1/4t) location in the vessel wall?
Response
The 4.57°F term is a correction factor to reflect the difference in the temperature differential analysis performed with the adjusted reference temperature (ART) values used in the April 15, 2009 submittal and the revised ART values used in the December 18, 2009 submittal. The temperature differential would be slightly different for the two different ART values, at the reactor coolant temperature corresponding to each ART value. The 4.57°F term is the difference between the ART values determined by the two different methods for the limiting material. The 4.57°F would bound the actual difference between the temperature differential values for the two different ART values.
Attachment L-1 0-278 Page 2 of 3 NRC Staff Question 3 Confirm that the 28.77°F temperature differential is from the reactor coolant to the 1/4t location versus the 3/4t location and that the 1/4t location is the controlling location for the DBNPS reactor vessel during heatup with respect to allowable pressure.
Response
The 28.77°F temperature differential is the reactor coolant to the 1/4t location versus the 3/4t location. The 1/4t location is the controlling location for the DBNPS reactor vessel during heatup with respect to allowable pressure.
NRC Staff Question 4 Confirm that the chemistry factors used to calculate the ART for welds WF-182-1 and WF-233 were determined from the RG 1.99, Rev. 2 tables rather than using the minimum chemistry factor of 167 required by the staff safety evaluation of BAW-2308.
Response
The chemistry factors were determined using the Regulatory Guide 1.99, "RADIATION EMBRITTLEMENT OF REACTOR VESSEL MATERIALS," Revision 2 tables.
NRC Staff Question 5 Page 10 of 16 of Enclosure A to the December 18, 2009 submittal provides an uncorrected maximum pressure value of 625 psig below 235'F. This is different from the currently approved P-T curves for Davis Besse. Is the 625OF [correct unit is psig] value from the new PTLR that has not yet been submitted to the NRC?
Response
Yes, the 625 pounds per square inch (psig) value is the uncorrected value for the maximum pressure below 235OF from the new.PTLR. However, in the new PTLR the pressure appearing on the P-T curves will be the corrected pressure (corrected for the actual measurement location), which is lower.
Attachment L-10-278 Page 3 of 3 References
- 1. Letter from Barry S. Allen to NRC dated April 15, 2009,
Subject:
"Davis-Besse Nuclear Power Station, Unit No. 1, Docket No. 50-346, License No. NPF-3, License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50, Appendix G" (ADAMS Accession No. ML091130228).
- 2. Letter from Barry S. Allen to NRC dated December 18, 2009,
Subject:
"Davis-Besse Nuclear Power Station, Unit No. 1, Docket No. 50-346, License No. NPF-3, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and-Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50, Appendix G (TAC No. ME1 127 - License Amendment Request, ME-1 128 Exemption Request)" (ADAMS Accession No. ML093570103).
- 3. Letter from Barry S. Allen to NRC dated August 26, 2010,
Subject:
"Davis-Besse Nuclear Power Station, Docket No. 50-346, License No. NPF-3, Response to a Request for Additional Information Related to a License Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements Contained In 10 CFR 50.61and 10 CFR 50, Appendix G (TAC NOS. ME1127 and 1128)."
