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| {{#Wiki_filter:June 20, 2008 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760 | | {{#Wiki_filter:June 20, 2008 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398) | | DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398) |
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| ==Dear Mr. Allen:== | | ==Dear Mr. Allen:== |
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| By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in "Standard Technical Specifications Babcock and Wilcox (B&W) Plants," Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004. | | By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004. |
| | | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter. |
| The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter. | | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. |
| | | Sincerely, |
| The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC | | /RA/ |
| =s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. | | Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 |
| Sincerely, /RA/ | |
| Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| Docket No. 50-346 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information | | Request for Additional Information cc w/encl: See next page |
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| cc w/encl: See next page Mr. Barry S. Allen June 20, 2008 Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
| | Mr. Barry S. Allen June 20, 2008 Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398) | | DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398) |
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| ==Dear Mr. Allen:== | | ==Dear Mr. Allen:== |
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| By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in "Standard Technical Specifications Babcock and Wilcox (B&W) Plants," Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004. | | By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004. |
| | | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter. |
| The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter. | | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. |
| | | Sincerely, |
| The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC | | /RA/ |
| =s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. | | Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 |
| Sincerely, /RA/ Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| Docket No. 50-346 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/encl: See next page DISTRIBUTION: | | Request for Additional Information cc w/encl: See next page DISTRIBUTION: |
| PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMCGoodwin RidsNrrPMTWengert RidsNrrLAEWhitt RidsAcrsAcnw&mMailCenter RidsNrrDirsItsb RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ALewin, NRR ADAMS Accession Number: | | PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMCGoodwin RidsNrrPMTWengert RidsNrrLAEWhitt RidsAcrsAcnw&mMailCenter RidsNrrDirsItsb RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ALewin, NRR ADAMS Accession Number: ML081650364 OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGoodwin TWengert EWhitt RGibbs DATE 6/19/08 6/19/08 6/19/08 6/20/08 OFFICIAL RECORD COPY |
| ML081650364 | |
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| OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA LPL3-2/BC | |
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| NAME CGoodwin TWengert EWhitt RGibbs DATE 6/19/08 6/19/08 6/19/08 6/20/08 OFFICIAL RECORD COPY Davis-Besse Nuclear Power Station, Unit No. 1 | |
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| cc: Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3065 5501 North State Route 2 Oak Harbor, OH 43449-9760
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| Director, Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009
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| Resident Inspector U.S. Nuclear Regulatory Commission 5503 North State Route 2 Oak Harbor, OH 43449-9760
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| Stephen Helmer Supervisor, Technical Support Section Bureau of Radiation Protection Ohio Department of Health 35 East Chestnut Street, 7 th Floor Columbus, OH 43215
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| Carol O'Claire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-2206
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| Zack A. Clayton
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| DERR Ohio Environmental Protection Agency P.O. Box 1049 Columbus, OH 43266-0149
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| State of Ohio - Transportation Department Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573
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| Principal Assistant Attorney General Environmental Enforcement Section State Office Tower 30 East Broad Street, 25 th Floor Columbus, OH 43215
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| President, Board of County Commissioners of Ottawa County Port Clinton, OH 43252
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| President, Board of County Commissioners of Lucas County One Government Center, Suite 800 Toledo, OH 43604-6506
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| The Honorable Dennis J. Kucinich United States House of Representatives Washington, D.C. 20515
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| The Honorable Dennis J. Kucinich United States House of Representatives 14400 Detroit Avenue Lakewood, OH 44107
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| Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308
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| David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-15 76 South Main Street Akron, OH 44308
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| Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
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| Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308
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| Davis-Besse Nuclear Power Station, Unit No. 1 | | Davis-Besse Nuclear Power Station, President, Board of County Unit No. 1 Commissioners of Ottawa County Port Clinton, OH 43252 cc: |
| | Manager, Site Regulatory Compliance President, Board of County FirstEnergy Nuclear Operating Company Commissioners of Lucas County Davis-Besse Nuclear Power Station One Government Center, Suite 800 Mail Stop A-DB-3065 Toledo, OH 43604-6506 5501 North State Route 2 Oak Harbor, OH 43449-9760 The Honorable Dennis J. Kucinich United States House of Representatives Director, Ohio Department of Commerce Washington, D.C. 20515 Division of Industrial Compliance Bureau of Operations & Maintenance The Honorable Dennis J. Kucinich 6606 Tussing Road United States House of Representatives P.O. Box 4009 14400 Detroit Avenue Reynoldsburg, OH 43068-9009 Lakewood, OH 44107 Resident Inspector U.S. Nuclear Regulatory Commission Joseph J. Hagan 5503 North State Route 2 President and Chief Nuclear Officer Oak Harbor, OH 43449-9760 FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 Stephen Helmer 76 South Main Street Supervisor, Technical Support Section Akron, OH 44308 Bureau of Radiation Protection Ohio Department of Health David W. Jenkins, Attorney 35 East Chestnut Street, 7th Floor FirstEnergy Corporation Columbus, OH 43215 Mail Stop A-GO-15 76 South Main Street Carol OClaire, Chief, Radiological Branch Akron, OH 44308 Ohio Emergency Management Agency 2855 West Dublin Granville Road Danny L. Pace Columbus, OH 43235-2206 Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Zack A. Clayton Mail Stop A-GO-14 DERR 76 South Main Street Ohio Environmental Protection Agency Akron, OH 44308 P.O. Box 1049 Columbus, OH 43266-0149 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company State of Ohio - Transportation Department Mail Stop A-GO-2 Public Utilities Commission 76 South Main Street 180 East Broad Street Akron, OH 44308 Columbus, OH 43266-0573 Principal Assistant Attorney General Environmental Enforcement Section State Office Tower 30 East Broad Street, 25th Floor Columbus, OH 43215 |
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| cc: | | Davis-Besse Nuclear Power Station, Unit No. 1 cc: |
| | Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 |
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| Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308
| | REQUEST FOR ADDITIONAL INFORMATION DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 In reviewing the FirstEnergy Nuclear Operating Company=s submittal dated August 3, 2007 (Agencywide Documents Access and Management System Accession No. ML0722004510), |
| | | related to revising the current technical specifications (CTS) to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1, for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), the NRC staff has determined that the following information is needed in order to complete its review: |
| Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
| | A. Surveillance Requirement (SR) for Emergency Feedwater (EFW) System Steam Generator (SG) Control System |
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| Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
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| James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
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| Enclosure REQUEST FOR ADDITIONAL INFORMATION
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| DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 | |
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| DOCKET NO. 50-346 | |
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| In reviewing the FirstEnergy Nuclear Operating Company | |
| =s submittal dated August 3, 2007 (Agencywide Documents Access and Management System Accession No. ML0722004510), related to revising the current technical specifications (CTS) to the improved technical specifications consistent with improved standard technical specifications (STS) as described in "Standard Technical Specifications Babcock and Wilcox (B&W) Plants", Revision 3.1, for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), the NRC staff has determined that the following information is needed in order to complete its review: | |
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| 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). | | : 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. | | : 2. Please provide analyses to demonstrate that the EFW System would be operable without performing CTS SR 4.7.1.2.1.d. |
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| ===
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| Background===
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| Criterion 3 of 10 CFR 50.36(d)(2)(ii) states that a TS limiting condition for operation (LCO) of a nuclear reactor must be established for "a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."
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| The EFW System is retained in the TSs per Criterion 3 of 10 CFR 50.36(d)(2)(ii). Current TSs require the EFW System SG Level Control System to be operable in order for the EFW to be capable of mitigating small break Loss of Coolant Accidents.
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| Section 50.36(d)(3) of 10 CFR states that TSs will include SRs which "are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limit s, and that the limiting conditions for operation will be met."
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| SR 4.7.1.2.1.d contains testing, calibrations, and inspections associated with the EFW SG Level Control. It is unclear how the proposed deletion of SR 4.7.1.2.1.d from TSs will assure that the necessary quality of the EFW SG Level Controls are maintained, so that facility operation will be within safety limits, and that the LCOs will be met per 10 CFR 50.36(d)(3).
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| B. LCO for Remote Shutdown Control Circuits and Transfer Switches
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| : 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.
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| ===
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| Background===
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| LCO 3.3.3.5.2 requires that the control circuits and transfer switches be operable during Modes 1, 2, and 3. The control circuits and transfer switches provide the operator with sufficient instrumentation and controls to place and maintain the unit in a safe shutdown condition from
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| locations other than the control room. This capability provides protection against the possibility of the control room becoming inaccessible.
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| NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants," which provides guidance to NRC staff, contains LCO 3.3.18, "Remote Shutdown System." The STS Bases for LCO 3.3.18 states that the Remote Shutdown System satisfies Criterion 4 of 10 CFR 50.36(d)(2)(ii).
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| Criterion 4 of 10 CFR 50.36(d)(2)(ii) states that a TS LCO of a nuclear reactor must be established for "a structure, system, or component which operating exper ience or probabilistic risk assessment has shown to be significant to public health and safety." | | ===Background=== |
| | Criterion 3 of 10 CFR 50.36(d)(2)(ii) states that a TS limiting condition for operation (LCO) of a nuclear reactor must be established for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. |
| | The EFW System is retained in the TSs per Criterion 3 of 10 CFR 50.36(d)(2)(ii). Current TSs require the EFW System SG Level Control System to be operable in order for the EFW to be capable of mitigating small break Loss of Coolant Accidents. |
| | Section 50.36(d)(3) of 10 CFR states that TSs will include SRs which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. |
| | SR 4.7.1.2.1.d contains testing, calibrations, and inspections associated with the EFW SG Level Control. It is unclear how the proposed deletion of SR 4.7.1.2.1.d from TSs will assure that the necessary quality of the EFW SG Level Controls are maintained, so that facility operation will be within safety limits, and that the LCOs will be met per 10 CFR 50.36(d)(3). |
| | Enclosure |
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| The licensee has pointed out that the basis for this LCO in their CTS is fire protection. However, the NRC staff notes that Generic Letter (GL) 88-12, "Removal of Fire Protection Requirements from Technical Specifications," dated August 2, 1988, provided specific guidance on the removal of fire protection requirements from TSs. Although the NRC staff endorsed the removal of fire protection requirements from TSs, GL 88-12 stated that "any specifications related to the capability for safe shutdown following a fire, e.g., see Item 8(j) in En closure 1 to GL 81-12, are to be retained in TS." Thus, GL 88-12 clearly supports the NRC staff's position that the remote shutdown capability m eets Criterion 4 of 10 CFR 50.36(d)(2)(ii), and should be retained in the DBNPS TSs.
| | 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. |
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| | ===Background=== |
| | LCO 3.3.3.5.2 requires that the control circuits and transfer switches be operable during Modes 1, 2, and 3. The control circuits and transfer switches provide the operator with sufficient instrumentation and controls to place and maintain the unit in a safe shutdown condition from locations other than the control room. This capability provides protection against the possibility of the control room becoming inaccessible. |
| | NUREG-1430, Standard Technical Specifications Babcock and Wilcox Plants, which provides guidance to NRC staff, contains LCO 3.3.18, Remote Shutdown System. The STS Bases for LCO 3.3.18 states that the Remote Shutdown System satisfies Criterion 4 of 10 CFR 50.36(d)(2)(ii). |
| | Criterion 4 of 10 CFR 50.36(d)(2)(ii) states that a TS LCO of a nuclear reactor must be established for a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. |
| | The licensee has pointed out that the basis for this LCO in their CTS is fire protection. However, the NRC staff notes that Generic Letter (GL) 88-12, Removal of Fire Protection Requirements from Technical Specifications, dated August 2, 1988, provided specific guidance on the removal of fire protection requirements from TSs. Although the NRC staff endorsed the removal of fire protection requirements from TSs, GL 88-12 stated that any specifications related to the capability for safe shutdown following a fire, e.g., see Item 8(j) in Enclosure 1 to GL 81-12, are to be retained in TS. Thus, GL 88-12 clearly supports the NRC staffs position that the remote shutdown capability meets Criterion 4 of 10 CFR 50.36(d)(2)(ii), and should be retained in the DBNPS TSs. |
| It is unclear how the deletion of CTS LCO 3.3.3.5.2, which removes the capability for remote shutdown from the TSs, is in accordance with 10 CFR 50.36(d)(2)(ii), which requires TSs for items meeting Criterion 4.}} | | It is unclear how the deletion of CTS LCO 3.3.3.5.2, which removes the capability for remote shutdown from the TSs, is in accordance with 10 CFR 50.36(d)(2)(ii), which requires TSs for items meeting Criterion 4.}} |
Letter Sequence 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
[Table View] |
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Category:Letter
MONTHYEARML24303A3282024-10-29029 October 2024
Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection
ML24281A0662024-10-0404 October 2024
EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components
IR 05000346/20244032024-09-27027 September 2024
Security Baseline Inspection Report 05000346/2024403
ML24269A0552024-09-25025 September 2024
Submittal of the Updated Final Safety Analysis Report, Revision 35
05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024
Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
ML24134A1522024-09-17017 September 2024
Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter
ML24260A2382024-09-16016 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24255A8032024-09-11011 September 2024
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1602024-09-0505 September 2024
Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station
L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024
Submittal of Quality Assurance Program Manual, Revision 30
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
IR 05000346/20240052024-08-22022 August 2024
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005)
L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024
Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
IR 05000346/20240022024-08-0101 August 2024
Integrated Inspection Report 05000346/2024002
IR 05000346/20244012024-07-30030 July 2024
Security Baseline Inspection Report 05000346/2024401
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024
Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report
L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024
License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024
Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024
Unit No.1 - Report of Facility Changes, Tests, and Experiments
ML24142A3532024-05-21021 May 2024
Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023
L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024
Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024
Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage
IR 05000346/20240012024-05-0303 May 2024
Integrated Inspection Report 05000346/2024001
L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024
Occupational Radiation Exposure Report for Year 2023
L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024
Submittal of Core Operating Limits Report, Cycle 24, Revision 0
ML24089A2582024-04-0101 April 2024
Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010
L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024
Annual Notification of Property Insurance Coverage
ML24036A3472024-03-0707 March 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24057A0752024-03-0101 March 2024
The Associated Independent Spent Fuel Storage Installations
ML24057A3362024-02-28028 February 2024
Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006)
IR 05000346/20230062024-02-28028 February 2024
Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006)
L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024
Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule
CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024
Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions
L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
IR 05000346/20243012024-02-0202 February 2024
NRC Initial License Examination Report 05000346/2024301
IR 05000346/20230042024-01-31031 January 2024
Integrated Inspection Report 05000346/2023004
ML23313A1352024-01-17017 January 2024
Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program
ML23353A1192023-12-19019 December 2023
Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
IR 05000346/20234032023-11-0202 November 2023
Security Baseline Inspection Report 05000346/2023403
ML23293A0612023-11-0101 November 2023
Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant
ML24045A0322023-10-26026 October 2023
L-23-221 Proposed Exam Submittal Cover Letter
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24274A1482024-09-30030 September 2024
NRR E-mail Capture - Davis-Besse - RAI Re Relief Request L-23-214
ML24260A2382024-09-16016 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24249A1602024-09-0505 September 2024
Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station
ML24204A0012024-07-17017 July 2024
NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports
ML24142A3532024-05-21021 May 2024
Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML24089A2582024-04-0101 April 2024
Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
IR 05000346/20234022023-07-13013 July 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402
ML23131A2732023-05-15015 May 2023
Notification of NRC Supplemental Inspection 95001 and Request for Information
ML23033A0322023-02-0101 February 2023
NRR E-mail Capture - Request for Additional Information for Davis-Besses 2022 Steam Generator Inspection Report (L-2022-LRO-0115)
ML22357A0302022-12-23023 December 2022
Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000346/2023010
ML22266A1102022-09-23023 September 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure
ML22214A7042022-08-0202 August 2022
Reissue - Davis-Besse Nuclear Power Station, Unit 1 Notification of Nrc Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011
ML22187A0992022-07-0606 July 2022
Notification of NRC Supplemental Inspection (95001) and Request for Information
ML22164A8572022-06-13013 June 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan
ML22118A6862022-04-28028 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval
ML22112A1092022-04-22022 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
ML22055A0872022-02-23023 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3
IR 05000346/20210912021-12-17017 December 2021
NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding
ML21321A3792021-11-16016 November 2021
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval
ML21301A0992021-10-28028 October 2021
Draft Request for Additional Information: Proposed Alternate for Examination of Steam Generator Welds - Energy Harbor Nuclear Corp., Davis-Besse Nuclear Power Station, Unit No. 1
ML21203A3252021-07-28028 July 2021
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000346/2021011
ML21155A1952021-06-0404 June 2021
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Davis Besse Nuclear Power Station
ML21041A5452021-02-10010 February 2021
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports
ML21007A3732021-01-0707 January 2021
NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff,
ML21004A1442020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff
ML20300A5592020-10-27027 October 2020
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML20154K7642020-06-0202 June 2020
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425
ML20133J9792020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML20127H8672020-05-0606 May 2020
NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
ML20021A3162020-01-21021 January 2020
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing
ML19192A2222019-07-18018 July 2019
Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19179A1382019-06-28028 June 2019
NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program
ML19164A1532019-06-13013 June 2019
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan
ML19162A3922019-06-11011 June 2019
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications
ML19143A0732019-05-29029 May 2019
FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments
ML18305B0192018-11-0101 November 2018
18 Davis-Besse Nuclear Power Station - Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information(Rdb)
ML18201A4122018-07-19019 July 2018
NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML18190A4902018-07-0909 July 2018
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team), Inspection Report 05000346/2018011 (DRP-DXB)
ML18102B0852018-04-12012 April 2018
NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver
ML18043A0102018-02-0909 February 2018
NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans
ML17355A3722017-12-21021 December 2017
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML17303B1582017-11-0707 November 2017
FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information
ML17257A1402017-09-14014 September 2017
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML17135A3612017-05-12012 May 2017
Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000346/2017010 (Jvb)
ML17129A4112017-05-0909 May 2017
Request for Additional Information Regarding Evaluation Submitted in Response to License Renewal Commitment No. 54
ML17100A1732017-04-19019 April 2017
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805
ML16364A2792017-01-23023 January 2017
Request for Additional Information Regarding License Renewal Commitment No. 42
ML16355A0352016-12-19019 December 2016
Ltr 12/19/16 Davis-Besse Nuclear Power Station, Unit 1 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000346/2017009 (Bxj)
ML16256A0662016-10-18018 October 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805
2024-09-05
[Table view] |
Text
June 20, 2008 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398)
Dear Mr. Allen:
By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Barry S. Allen June 20, 2008 Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO IMPROVED TECHNICAL SPECIFICATIONS CONVERSION (MD6398)
Dear Mr. Allen:
By letter to the Nuclear Regulatory Commission (NRC) dated August 3, 2007, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to an application requesting to amend the operating license, for the Davis-Besse Nuclear Power Station, Unit No. 1. FENOC has proposed to revise the current technical specifications to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1. STS Revision 3.1 is the December, 2005, update to NUREG-1430, which was published June 2004.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMCGoodwin RidsNrrPMTWengert RidsNrrLAEWhitt RidsAcrsAcnw&mMailCenter RidsNrrDirsItsb RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ALewin, NRR ADAMS Accession Number: ML081650364 OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGoodwin TWengert EWhitt RGibbs DATE 6/19/08 6/19/08 6/19/08 6/20/08 OFFICIAL RECORD COPY
Davis-Besse Nuclear Power Station, President, Board of County Unit No. 1 Commissioners of Ottawa County Port Clinton, OH 43252 cc:
Manager, Site Regulatory Compliance President, Board of County FirstEnergy Nuclear Operating Company Commissioners of Lucas County Davis-Besse Nuclear Power Station One Government Center, Suite 800 Mail Stop A-DB-3065 Toledo, OH 43604-6506 5501 North State Route 2 Oak Harbor, OH 43449-9760 The Honorable Dennis J. Kucinich United States House of Representatives Director, Ohio Department of Commerce Washington, D.C. 20515 Division of Industrial Compliance Bureau of Operations & Maintenance The Honorable Dennis J. Kucinich 6606 Tussing Road United States House of Representatives P.O. Box 4009 14400 Detroit Avenue Reynoldsburg, OH 43068-9009 Lakewood, OH 44107 Resident Inspector U.S. Nuclear Regulatory Commission Joseph J. Hagan 5503 North State Route 2 President and Chief Nuclear Officer Oak Harbor, OH 43449-9760 FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 Stephen Helmer 76 South Main Street Supervisor, Technical Support Section Akron, OH 44308 Bureau of Radiation Protection Ohio Department of Health David W. Jenkins, Attorney 35 East Chestnut Street, 7th Floor FirstEnergy Corporation Columbus, OH 43215 Mail Stop A-GO-15 76 South Main Street Carol OClaire, Chief, Radiological Branch Akron, OH 44308 Ohio Emergency Management Agency 2855 West Dublin Granville Road Danny L. Pace Columbus, OH 43235-2206 Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Zack A. Clayton Mail Stop A-GO-14 DERR 76 South Main Street Ohio Environmental Protection Agency Akron, OH 44308 P.O. Box 1049 Columbus, OH 43266-0149 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company State of Ohio - Transportation Department Mail Stop A-GO-2 Public Utilities Commission 76 South Main Street 180 East Broad Street Akron, OH 44308 Columbus, OH 43266-0573 Principal Assistant Attorney General Environmental Enforcement Section State Office Tower 30 East Broad Street, 25th Floor Columbus, OH 43215
Davis-Besse Nuclear Power Station, Unit No. 1 cc:
Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
REQUEST FOR ADDITIONAL INFORMATION DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 In reviewing the FirstEnergy Nuclear Operating Company=s submittal dated August 3, 2007 (Agencywide Documents Access and Management System Accession No. ML0722004510),
related to revising the current technical specifications (CTS) to the improved technical specifications consistent with improved standard technical specifications (STS) as described in Standard Technical Specifications Babcock and Wilcox (B&W) Plants, Revision 3.1, for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), the NRC staff has determined that the following information is needed in order to complete its review:
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.
Background
Criterion 3 of 10 CFR 50.36(d)(2)(ii) states that a TS limiting condition for operation (LCO) of a nuclear reactor must be established for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The EFW System is retained in the TSs per Criterion 3 of 10 CFR 50.36(d)(2)(ii). Current TSs require the EFW System SG Level Control System to be operable in order for the EFW to be capable of mitigating small break Loss of Coolant Accidents.
Section 50.36(d)(3) of 10 CFR states that TSs will include SRs which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
SR 4.7.1.2.1.d contains testing, calibrations, and inspections associated with the EFW SG Level Control. It is unclear how the proposed deletion of SR 4.7.1.2.1.d from TSs will assure that the necessary quality of the EFW SG Level Controls are maintained, so that facility operation will be within safety limits, and that the LCOs will be met per 10 CFR 50.36(d)(3).
Enclosure
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.
Background
LCO 3.3.3.5.2 requires that the control circuits and transfer switches be operable during Modes 1, 2, and 3. The control circuits and transfer switches provide the operator with sufficient instrumentation and controls to place and maintain the unit in a safe shutdown condition from locations other than the control room. This capability provides protection against the possibility of the control room becoming inaccessible.
NUREG-1430, Standard Technical Specifications Babcock and Wilcox Plants, which provides guidance to NRC staff, contains LCO 3.3.18, Remote Shutdown System. The STS Bases for LCO 3.3.18 states that the Remote Shutdown System satisfies Criterion 4 of 10 CFR 50.36(d)(2)(ii).
Criterion 4 of 10 CFR 50.36(d)(2)(ii) states that a TS LCO of a nuclear reactor must be established for a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The licensee has pointed out that the basis for this LCO in their CTS is fire protection. However, the NRC staff notes that Generic Letter (GL) 88-12, Removal of Fire Protection Requirements from Technical Specifications, dated August 2, 1988, provided specific guidance on the removal of fire protection requirements from TSs. Although the NRC staff endorsed the removal of fire protection requirements from TSs, GL 88-12 stated that any specifications related to the capability for safe shutdown following a fire, e.g., see Item 8(j) in Enclosure 1 to GL 81-12, are to be retained in TS. Thus, GL 88-12 clearly supports the NRC staffs position that the remote shutdown capability meets Criterion 4 of 10 CFR 50.36(d)(2)(ii), and should be retained in the DBNPS TSs.
It is unclear how the deletion of CTS LCO 3.3.3.5.2, which removes the capability for remote shutdown from the TSs, is in accordance with 10 CFR 50.36(d)(2)(ii), which requires TSs for items meeting Criterion 4.
