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| | issue date = 06/20/2008 | | | issue date = 06/20/2008 |
| | title = RAI Related to Improved Technical Specifications Conversion | | | title = RAI Related to Improved Technical Specifications Conversion |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-2 |
| | addressee name = Allen B S | | | addressee name = Allen B |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000346 | | | docket = 05000346 |
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| =Text= | | =Text= |
| {{#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
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| cc:
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| Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308
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| Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
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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
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| =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
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| : 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).
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| : 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===
| |
| 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
| | 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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| locations other than the control room. This capability provides protection against the possibility of the control room becoming inaccessible.
| | 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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| 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).
| | 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. |
|
| |
|
| 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 |
|---|
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
|
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] |
|
|---|
Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024
NRC Initial License Examination Report 05000346/2024301
IR 05000346/20230042024-01-31031 January 2024
Integrated Inspection Report 05000346/2023004
ML23313A1352024-01-17017 January 2024
Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program
ML23353A1192023-12-19019 December 2023
Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
IR 05000346/20234032023-11-0202 November 2023
Security Baseline Inspection Report 05000346/2023403
ML23293A0612023-11-0101 November 2023
Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000346/20234012023-09-13013 September 2023
Security Baseline Inspection Report 05000346/2023401 (Public)
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
IR 05000346/20230112023-08-30030 August 2023
Biennial Problem Identification and Resolution Inspection Report 05000346/2023011
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000346/20230052023-08-24024 August 2023
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005)
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
IR 05000346/20230502023-08-0303 August 2023
Special Inspection Report 05000346/2023050
IR 05000346/20230902023-08-0101 August 2023
EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public)
ML23178A2742023-08-0101 August 2023
Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
IR 05000346/20230022023-07-27027 July 2023
Integrated Inspection Report 05000346/2023002
ML23193A7842023-07-13013 July 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
ML23160A2342023-06-13013 June 2023
Confirmation of Initial License Examination
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
IR 05000346/20235012023-06-13013 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
ML23131A2732023-05-15015 May 2023
Notification of NRC Supplemental Inspection 95001 and Request for Information
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
IR 05000346/20230102023-05-0909 May 2023
Commercial Grade Dedication Inspection Report 05000346/2023010
ML23123A1272023-05-0303 May 2023
Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station
IR 05000346/20230012023-05-0101 May 2023
Integrated Inspection Report 05000346/2023001 and 07200014/2022001
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
ML23111A1972023-04-26026 April 2023
Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station
ML23114A1062023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23096A1382023-04-11011 April 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
ML23066A2892023-03-14014 March 2023
Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement
ML23066A2592023-03-14014 March 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1
2024-02-02
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
ML23193A7842023-07-13013 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-Besse's 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
ML16196A0152016-07-22022 July 2016
Request for Additional Information Regarding Amendment Request to Revise Emergency Action Level Scheme
L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-06-24024 June 2016
Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML16060A0122016-02-29029 February 2016
FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120
ML16047A1452016-02-22022 February 2016
Supplemental Information Needed for Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805
ML16019A3972016-01-20020 January 2016
Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements
ML15222A1792015-09-21021 September 2015
Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements (TAC No. MF6060)(L-15-117)
2023-07-13
[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.
