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| {{#Wiki_filter:FENOC ft 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President | | {{#Wiki_filter:FENOC ft 5501 North State Route 2 FirstEnergyNuclear OperatingCompany Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 July23, 2008 L-08-221 10 CFR 50.90 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001 |
| -Nuclear Fax: 419-321-7582 July23, 2008 L-08-221 10 CFR 50.90 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Response to Request for Additional Information Related to Improved Technical Specifications Conversion, (TAC No. MD6398)By letter dated August 3, 2007, as supplemented by letters dated May 16, 2008 (2 letters), the FirstEnergy Nuclear Operating Company (FENOC) submitted an application for license amendment. | | |
| The proposed amendment would revise the Operating License and Technical Specifications for the Davis-Besse Nuclear Power Station (DBNPS) in order to convert from Current Technical Specifications (CTS) to Improved Technical Specifications (ITS).By letter dated June 20, 2008, the Nuclear Regulatory Commission (NRC) staff requested additional information necessary to complete the amendment application review. The FENOC responses to the NRC staff's questions contained in the information request are attached.In order to address the issues in the request for additional information, FENOC has made changes to the proposed Improved Technical Specifications. | | Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Response to Request for Additional Information Related to Improved Technical Specifications Conversion, (TAC No. MD6398) |
| Details of the proposed changes were provided by FENOC on the NRC and DBNPS ITS Conversion Website. The associated question threads have been closed by the NRC after their review. The final changes will be included within the Revision 1 supplement for the affected ITS Volumes.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) 761-6071.fv) | | By letter dated August 3, 2007, as supplemented by letters dated May 16, 2008 (2 letters), the FirstEnergy Nuclear Operating Company (FENOC) submitted an application for license amendment. The proposed amendment would revise the Operating License and Technical Specifications for the Davis-Besse Nuclear Power Station (DBNPS) in order to convert from Current Technical Specifications (CTS) to Improved Technical Specifications (ITS). |
| Davis-Besse Nuclear Power Station L-08-221 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on U/6", 3 ..Sincerely, rrry S. Allen | | By letter dated June 20, 2008, the Nuclear Regulatory Commission (NRC) staff requested additional information necessary to complete the amendment application review. The FENOC responses to the NRC staff's questions contained in the information request are attached. |
| | In order to address the issues in the request for additional information, FENOC has made changes to the proposed Improved Technical Specifications. Details of the proposed changes were provided by FENOC on the NRC and DBNPS ITS Conversion Website. The associated question threads have been closed by the NRC after their review. The final changes will be included within the Revision 1 supplement for the affected ITS Volumes. |
| | 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) 761-6071. |
| | fv) |
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| | Davis-Besse Nuclear Power Station L-08-221 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on U/6", 3 .. |
| | Sincerely, rrry S. Allen |
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| ==Attachment:== | | ==Attachment:== |
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| Response to Request for Additional Information Related to Improved Technical Specifications Conversion cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison) | | Response to Request for Additional Information Related to Improved Technical Specifications Conversion cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison) |
| Attachment L-08-221 Response to Request for Additional Information Related to Improved Technical Specifications Conversion Page 1 of 1 To complete their review, the NRC staff has requested additional information regarding the license amendment application for the conversion of Current Technical Specifications to Improved Technical Specifications. | | |
| The staff request is provided below in bold type followed by the FENOC response for DBNPS.A. Surveillance Requirement (SR) for Emergency Feedwater (EFW) System Steam Generator (SG) Control System 1. Please provide a basis that demonstrates how removal of the current SR 4.7.1.2.1.d from the Technical Specifications (TSs) would be in compliance with Title 10 of the Code of Federal Regulations (10 CFR) 50.36 (d)(3).2. Please provide analyses to demonstrate that the EFW System would be operable without performing CTS SR 4.7.1.2.1.d. | | Attachment L-08-221 Response to Request for Additional Information Related to Improved Technical Specifications Conversion Page 1 of 1 To complete their review, the NRC staff has requested additional information regarding the license amendment application for the conversion of Current Technical Specifications to Improved Technical Specifications. The staff request is provided below in bold type followed by the FENOC response for DBNPS. |
| It has been determined that CTS SR 4.7.1.2.1 .d will not be removed from Technical Specifications. | | A. Surveillance Requirement (SR) for Emergency Feedwater (EFW) System Steam Generator (SG) Control System |
| CTS SR 4.7.1.2.1 .d will be retained in ITS 3.7.5, Emergency Feedwater (EFW). Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website.B. LCO for Remote Shutdown Control Circuits and Transfer Switches 1. Please provide a basis that demonstrates how removal of the CTS LCO 3.3.3.5.2 from the TSs would be in compliance with 10 CFR 50.36 (d)(2)(ii), Criterion 4.It has been determined that CTS LCO 3.3.3.5.2 will not be removed from Technical Specifications. | | : 1. Please provide a basis that demonstrates how removal of the current SR 4.7.1.2.1.d from the Technical Specifications (TSs) would be in compliance with Title 10 of the Code of FederalRegulations (10 CFR) 50.36 (d)(3). |
| CTS LCO 3.3.3.5.2, and the associated actions and surveillance requirements will be retained in ITS 3.3.18, Remote Shutdown System. Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website.}} | | : 2. Please provide analyses to demonstrate that the EFW System would be operable without performing CTS SR 4.7.1.2.1.d. |
| | It has been determined that CTS SR 4.7.1.2.1 .d will not be removed from Technical Specifications. CTS SR 4.7.1.2.1 .d will be retained in ITS 3.7.5, Emergency Feedwater (EFW). Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website. |
| | B. LCO for Remote Shutdown Control Circuits and Transfer Switches |
| | : 1. Please provide a basis that demonstrates how removal of the CTS LCO 3.3.3.5.2 from the TSs would be in compliance with 10 CFR 50.36 (d)(2)(ii), |
| | Criterion 4. |
| | It has been determined that CTS LCO 3.3.3.5.2 will not be removed from Technical Specifications. CTS LCO 3.3.3.5.2, and the associated actions and surveillance requirements will be retained in ITS 3.3.18, Remote Shutdown System. Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website.}} |
Letter Sequence Response to RAI |
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TAC:MD6398, Increase Flexibility in Mode Restraints, Addition of LCO 3.0.8, Inoperability of Snubbers, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec, Changes to Reflect Revision of 10 CFR 50.55A, Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Correct Example 1.4-1, Containment Structural Integrity, TSTF-28, Correct LCO 3.0.6 Bases, Add Restriction for Lowest LOOP Tave During Mode 2 Physics Testing (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement
Results
Other: L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0, L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs, L-08-338, Copy of Improved Technical Specifications (ITS), L-08-378, Implementation of Improved Technical Specification Amendment No. 279, ML073531253, ML081350505, ML082000451, ML082270661, ML082270662, ML082270663, ML082270664, ML082270665, ML082270666, ML082270667, ML082270669, ML082270670, ML082600577, ML082840099, ML082900630, ML082900882, ML082910125
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MONTHYEARML0725600462007-09-11011 September 2007 9/11/2007-Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) - 9/11/2007 NRC Meeting Slides Project stage: Meeting ML0725600562007-09-12012 September 2007 9/12/2007 Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) 9/12/2007 NRC Meeting Slides Project stage: Meeting ML0729001172007-11-0707 November 2007 09/12/2007 - Meeting Summary with Fenco to Discuss Licensee'S ITS Conversion License Amendment Request for Davis-Besse Project stage: Meeting ML0735312532008-02-0404 February 2008 Improved Technical Specification Conversion Project stage: Other ML0814804652008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 5, (Revision 1), Section 3.0 - LCO and SR Applicability Project stage: Request ML0801400252008-05-16016 May 2008 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Opportunity for a Hearing (Tac Nos. MD6319-MD3622, MD6324-MD6333, MD6398-MD6403, MD6644-MD6649, and MD6684) Project stage: Acceptance Review L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.02008-05-16016 May 2008 Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0 Project stage: Other L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 Project stage: Supplement ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features Project stage: Request ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems Project stage: Request ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) Project stage: Request ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits Project stage: Request ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems Project stage: Request ML0826005772008-05-30030 May 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website Project stage: Other ML0813505052008-06-17017 June 2008 Improved Technical Specifications Conversion Milestone Schedule Project stage: Other ML0815705882008-06-18018 June 2008 Request for Additional Information Related to Improved Technical Specifications Conversion Project stage: RAI ML0816503642008-06-20020 June 2008 RAI Related to Improved Technical Specifications Conversion Project stage: RAI L-08-221, Response to Request for Additional Information Related to Improved Technical Specifications Conversion2008-07-23023 July 2008 Response to Request for Additional Information Related to Improved Technical Specifications Conversion Project stage: Response to RAI ML0822706582008-08-0707 August 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications to Improved Technical Specifications - Volumes 1, 2, 3, 4, 8, 10, 12, 13, 14, and 16 Project stage: Supplement L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations2008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations Project stage: Request ML0822706612008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 1, Revision 1, Application of Selection Criteria to the Dbnps Technical Specifications Project stage: Other ML0822706622008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 2, Revision 1, Generic Determination of No Significant Hazards Consideration and Environmental Assessment Project stage: Other ML0822706672008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 16, Revision 1, ITS Chapter 5.0, Administrative Controls Project stage: Other ML0822706702008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 13, Revision 1, ITS Section 3.8, Electrical Power Systems Project stage: Other ML0822706692008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 12, Revision 1, ITS Section 3.7, Plant Systems Project stage: Other ML0822706662008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 10, Revision 1, ITS Section 3.5, Emergency Core Cooling Systems Project stage: Other ML0822706652008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 8, Revision 1, Section 3.3 - Instrumentation Project stage: Other ML0822706642008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 4, Revision 1, ITS Chapter 2.0, Safety Limits Project stage: Other ML0822706632008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request Volume 3, Revision 1, ITS Chapter 1.0, Use and Application Project stage: Other L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs2008-08-26026 August 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs Project stage: Other L-08-224, Response to Request for Additional Information License Amendment Request to Convert Current Technical Specifications (CTS) to Improved Technical Specifications (Its), and Copy of Two Questions from NRC and Davis-Besse Its.2008-09-0303 September 2008 Response to Request for Additional Information License Amendment Request to Convert Current Technical Specifications (CTS) to Improved Technical Specifications (Its), and Copy of Two Questions from NRC and Davis-Besse Its. Project stage: Response to RAI ML0824903002008-10-0202 October 2008 ITSB Draft R, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902622008-10-0202 October 2008 Draft Safety Evaluation for Conversion to ITS with Beyond Scope Issues, (TAC MD Project stage: Draft Approval ML0824902712008-10-0202 October 2008 List of Acronyms to Davis Besse Draft Amend. ITS Conversion Project stage: Draft Other ML0824902752008-10-0202 October 2008 Draft a, Attachment to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902802008-10-0202 October 2008 ITSB Draft La, to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902892008-10-0202 October 2008 ITSB Draft L, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902952008-10-0202 October 2008 ITSB Draft M, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0828400992008-10-0808 October 2008 Assessment -Davis-Besse Nuclear Power Station, Unit No. 1 - Environmental Assessment and Finding of No Significant Impact for the Proposed Conversion to the Improved Technical Specifications (TAC 6398) Project stage: Other ML0820004512008-10-0808 October 2008 Environmental Assessment and Finding of No Significant Impact for the Proposed Conversion to the Improved Technical Specifications Project stage: Other L-08-338, Copy of Improved Technical Specifications (ITS)2008-10-21021 October 2008 Copy of Improved Technical Specifications (ITS) Project stage: Other ML0829006832008-11-20020 November 2008 Table A-DOC Attachment - Administrative Changes - to Davis-Besse Amend. ITS with Beyond Scope Issues Project stage: Acceptance Review ML0829007802008-11-20020 November 2008 ITSB L-Less Restrictive Changes - Attachment to Davis-Besse Amendment Beyond Scope Issues Project stage: Acceptance Review ML0829008822008-11-20020 November 2008 ITSB LA-Removed Details - Attachment to Davis-Besse Beyond Scope Issues Project stage: Other ML0829006302008-11-20020 November 2008 List of Acronyms to Davis-Besse Amend. Re; ITS with Beyond Scope Issues Project stage: Other ML0829101252008-11-20020 November 2008 ITSB R-Relocated Specifications - to Davis Besse Amendment Beyond Scope Issues Project stage: Other ML0829101122008-11-20020 November 2008 ITSB M - More Restrictive Changes - to Davis Besse Amendment Beyond Scope Issues Project stage: Acceptance Review ML0829006002008-11-20020 November 2008 Issuance of Amendment 279 for the Conversion to the Improved TSs with Beyond Scope Issues Project stage: Approval L-08-378, Implementation of Improved Technical Specification Amendment No. 2792008-12-16016 December 2008 Implementation of Improved Technical Specification Amendment No. 279 Project stage: Other 2008-02-04
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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
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FENOC ft 5501 North State Route 2 FirstEnergyNuclear OperatingCompany Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 July23, 2008 L-08-221 10 CFR 50.90 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Response to Request for Additional Information Related to Improved Technical Specifications Conversion, (TAC No. MD6398)
By letter dated August 3, 2007, as supplemented by letters dated May 16, 2008 (2 letters), the FirstEnergy Nuclear Operating Company (FENOC) submitted an application for license amendment. The proposed amendment would revise the Operating License and Technical Specifications for the Davis-Besse Nuclear Power Station (DBNPS) in order to convert from Current Technical Specifications (CTS) to Improved Technical Specifications (ITS).
By letter dated June 20, 2008, the Nuclear Regulatory Commission (NRC) staff requested additional information necessary to complete the amendment application review. The FENOC responses to the NRC staff's questions contained in the information request are attached.
In order to address the issues in the request for additional information, FENOC has made changes to the proposed Improved Technical Specifications. Details of the proposed changes were provided by FENOC on the NRC and DBNPS ITS Conversion Website. The associated question threads have been closed by the NRC after their review. The final changes will be included within the Revision 1 supplement for the affected ITS Volumes.
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) 761-6071.
fv)
Davis-Besse Nuclear Power Station L-08-221 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on U/6", 3 ..
Sincerely, rrry S. Allen
Attachment:
Response to Request for Additional Information Related to Improved Technical Specifications Conversion cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Attachment L-08-221 Response to Request for Additional Information Related to Improved Technical Specifications Conversion Page 1 of 1 To complete their review, the NRC staff has requested additional information regarding the license amendment application for the conversion of Current Technical Specifications to Improved Technical Specifications. The staff request is provided below in bold type followed by the FENOC response for DBNPS.
A. Surveillance Requirement (SR) for Emergency Feedwater (EFW) System Steam Generator (SG) Control System
- 1. Please provide a basis that demonstrates how removal of the current SR 4.7.1.2.1.d from the Technical Specifications (TSs) would be in compliance with Title 10 of the Code of FederalRegulations (10 CFR) 50.36 (d)(3).
- 2. Please provide analyses to demonstrate that the EFW System would be operable without performing CTS SR 4.7.1.2.1.d.
It has been determined that CTS SR 4.7.1.2.1 .d will not be removed from Technical Specifications. CTS SR 4.7.1.2.1 .d will be retained in ITS 3.7.5, Emergency Feedwater (EFW). Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website.
B. LCO for Remote Shutdown Control Circuits and Transfer Switches
- 1. Please provide a basis that demonstrates how removal of the CTS LCO 3.3.3.5.2 from the TSs would be in compliance with 10 CFR 50.36 (d)(2)(ii),
Criterion 4.
It has been determined that CTS LCO 3.3.3.5.2 will not be removed from Technical Specifications. CTS LCO 3.3.3.5.2, and the associated actions and surveillance requirements will be retained in ITS 3.3.18, Remote Shutdown System. Proposed changes have been provided to the NRC by FENOC on the NRC and DBNPS ITS Conversion Website.