Letter Sequence Other |
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MONTHYEARML0515301972005-06-0202 June 2005
6/2/05, Davis-Besse - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0603807252006-02-0909 February 2006
Request for Additional Information, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors
Project stage: RAI
L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-02-28028 February 2008
Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Supplement
ML0817803302008-07-10010 July 2008
Request for Additional Information Related to Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
L-10-111, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs.2010-04-30030 April 2010
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs.
Project stage: Supplement
L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013
Generic Safety Issue 191 Resolution Plan
Project stage: Other
L-13-224, Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the (DBNPS)2013-07-0303 July 2013
Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the (DBNPS)
Project stage: Other
ML21088A3442021-03-29029 March 2021
Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02
Project stage: Supplement
L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-022021-03-29029 March 2021
Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02
Project stage: Supplement
2008-07-10
[Table View] |
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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
FENOCTM 5501 North State Route 2
~
Oak Harbor. Ohio 43449 FirstEnergy Nuclear Operating Company Raymond A. Ueb 419-321-7676 Vice President, Nuclear Fax. 419-321-7582 July 3, 2013 10 CFR 50.54(f)
L-13-224 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 Number NPF-3 Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the Davis-Besse Nuclear Power Station, Unit No.1 (DBNPS)
(TAC No. MC4681)
By letter dated May 15, 2013 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML13135A456] (Reference 1), FirstEnergy Nuclear Operating Company (FENOC) provided the Davis-Besse Generic Safety Issue 191 Resolution Plan consistent with the Nuclear Energy Institute closure option template dated November 9,2012, "Closure Option Templates for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance". In Reference 1 FENOC committed to report on the progress toward confirming the strainer bypass percentage results is less than or equal to 15 grams of fiber per fuel assembly for DBNPS by July 15, 2013.
FENOC hereby submits the progress toward confirming the strainer bypass percentage results.
FENOC has obtained and reviewed strainer bypass test data from two other plants for applicability to the DBNPS strainer design. The relevant parameters from each test - debris bed thickness, approach velocity, and perforated plate hole size -
were compared to DBNPS parameters. Lower approach velocity and smaller strainer hole size associated with the test data could not be reconciled to DBNPS parameters given the available correlations. Based on this information, FENOC is reassessing the options to confirm the strainer bypass fraction . This item is documented and tracked in the FENOC activity tracking program.
By letter dated February 28,2008 (ML080650368), FENOC submitted a supplemental response to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" for DBNPS (Reference 2). By letter dated
Davis-Besse Nuclear Power Station, Unit No. 1 L-13-224 Page 2 of 3 July 10, 2008 (ML081780330), the Nuclear Regulatory Commission (NRC) staff requested FENOC to report how DBNPS has addressed the in-vessel downstream effects issue within 90-days of issuance of the final NRC Safety Evaluation (SE) on WCAP-16793. Reference 3 states:
FENOC may demonstrate that in-vessel downstream effects issues are resolved for DBNPS by showing that the licensee's plant conditions are bounded by the final WCAP-16793-NP and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE.
Alternately, FENOC may resolve this item by demonstrating, without reference to WCAP-16793 or the NRC staff SE, that in-vessel downstream effects have been addressed at DBNPS.
As indicated in Reference 1, FENOC intends to follow the resolution strategy proposed by the Pressurized Water Reactor Owners Group to establish in-vessel debris limits for the DBNPS type plant design and demonstrate that downstream effects have been addressed.
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, Manager, Fleet Licensing at (330) 315-6810.
Attachment:
cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
Davis-Besse Nuclear Power Station, Unit No.1 L-13-224 Page 3 of 3 References
- 1. FENOC letter to NRC, "Generic Safety Issue 191 Resolution Plan" (TAC No.
MC4681), May 15, 2013 (Accession No. ML13135A456).
- 2. FENOC letter to NRC, "Supplemental Response to Generic Letter 2004-02,
'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors'" (TAC No. MC4681),
February 28,2008 (Accession No. ML080650368).
- 3. NRC letter to FENOC, "Davis-Besse Nuclear Power Station, Unit No.1 - Request for Additional Information Related to Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No. MC4681)," July 10, 2008 (Accession No. ML081780330).
