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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 26. 2013 Mr. Raymond A. Ueb, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North Slate Route 2 Oak Harbor, OH 43449 |
| : 26. 2013 Mr. Raymond A. Ueb, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North Slate Route 2 Oak Harbor, OH 43449
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| ==SUBJECT:== | | ==SUBJECT:== |
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| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) |
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| ==Dear Mr. Lieb:== | | ==Dear Mr. Lieb:== |
| By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. | | By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review. the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. |
| The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." | |
| During its review. the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. | |
| Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov. | | Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov. |
| Docket No. 50-346 | | Docket No. 50-346 |
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| ==SUBJECT:== | | ==SUBJECT:== |
|
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| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) |
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| ==Dear Mr. Lieb:== | | ==Dear Mr. Lieb:== |
| By tetter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. | | By tetter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. |
| The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." | |
| During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. | |
| Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov. | | Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov. |
| Docket No. 50-346 | | Docket No. 50-346 |
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| .. "concurred via email OFFICE LA:DLR/RPB2* | | .. "concurred via email OFFICE LA:DLR/RPB2* |
| PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME I King JUri be YDiaz-Sanabria JUri be (SCuadrado for) DATE 11/25/13 11/25/13 11/26/13 11/26/13 OFFICIAL RECORD COPY RAI 3.0.3-3 DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION Issue: Loss of coating integrity for Service Levell II and Other coatings Industry operating experience (OE) indicates that degraded coatings have resulted in unanticipated or accelerated corrosion of the base metal and degraded performance of downstream equipment (e.g., reduction in flow, drop in pressure, reduction in heat transfer) due to flow blockage. | | PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME I King JUri be YDiaz-Sanabria JUri be (SCuadrado for) DATE 11/25/13 11/25/13 11/26/13 11/26/13 OFFICIAL RECORD COPY RAI 3.0.3-3 DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION Issue: Loss of coating integrity for Service Levell II and Other coatings Industry operating experience (OE) indicates that degraded coatings have resulted in unanticipated or accelerated corrosion of the base metal and degraded performance of downstream equipment (e.g., reduction in flow, drop in pressure, reduction in heat transfer) due to flow blockage. |
| Based on these industry OE examples, the staff has questions related to how the aging effect, loss of coating integrity due to blistering, | | Based on these industry OE examples, the staff has questions related to how the aging effect, loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage, would be managed for Service Levellll and Other coatings. |
| : cracking, flaking,
| | For purposes of this request for additional information (RAI): a. Service Levell II coatings are those installed on the interior of in-scope piping, heat exchanges, and tanks which support functions identified under Title 10 of the Code of Federal Regulations (CFR) 54.4(a)(1) and (a)(2). b. "Other coatings," include coatings installed on the interior of in-scope piping, heat exchangers, and tanks whose failure could prevent satisfactory accomplishment of any of the functions identilied under 10 CFR 54.4(a)(3). |
| : peeling, or physical damage, would be managed for Service Levellll and Other coatings.
| | : c. The term "coating" includes morganic (e.g., zinc-based) or organic (e.g., elastomeric or polymeric) coatings, linings (e.g., rubber, cementitious), and concrete surfacers that are designed to adhere to a component to protect its surface. d. The terms "paint" and "linings" should be considered as coatings. |
| For purposes of this request for additional information (RAI): a. Service Levell II coatings are those installed on the interior of in-scope piping, heat exchanges, and tanks which support functions identified under Title 10 of the Code of Federal Regulations (CFR) 54.4(a)(1) and (a)(2). b. "Other coatings," | | The staff believes that to effectively manage loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage of Service Levell II and Other coatings an aging management program should include: a. Baseline visual inspections of coatings installed on the interior surfaces of in-scope components should be conducted in the 1 0-year period prior to the period of extended operation |
| include coatings installed on the interior of in-scope piping, heat exchangers, and tanks whose failure could prevent satisfactory accomplishment of any of the functions identilied under 10 CFR 54.4(a)(3). | | : b. Subsequent periodic inspections where the interval is based on the baseline inspection results. For example: 1. If no peeling, delamination, blisters, or rusting are observed, and any cracking and flaking have been found acceptable, subsequent inspections could be conducted after multiple refueling outage intervals (e.g., for example six years, or more if the same coatings are in redundant trains}. ii. If the inspection results do not meet the above; but, a coating specialist has determined that no remediation is required, subsequent inspections could be conducted every other refueling outage interval. |
| : c. The term "coating" includes morganic (e.g., zinc-based) or organic (e.g., elastomeric or polymeric) | | 111. If coating degradation is observed that required repair or replacement, or for newly installed coatings, subsequent inspections should occur over the next two refueling outage intervals to establish a performance trend on the coatings. |
| : coatings, linings (e.g., rubber, cementitious),
| |
| and concrete surfacers that are designed to adhere to a component to protect its surface. | |
| : d. The terms "paint" and "linings" should be considered as coatings.
| |
| The staff believes that to effectively manage loss of coating integrity due to blistering, | |
| : cracking, flaking,
| |
| : peeling, or physical damage of Service Levell II and Other coatings an aging management program should include:
| |
| : a. Baseline visual inspections of coatings installed on the interior surfaces of in-scope components should be conducted in the 1 0-year period prior to the period of extended operation | |
| : b. Subsequent periodic inspections where the interval is based on the baseline inspection results. | |
| For example: | |
| : 1. If no peeling, delamination, | |
| : blisters, or rusting are observed, and any cracking and flaking have been found acceptable, subsequent inspections could be conducted after multiple refueling outage intervals (e.g., for example six years, or more if the same coatings are in redundant trains}.
| |
| ii. If the inspection results do not meet the above; but, a coating specialist has determined that no remediation is required, subsequent inspections could be conducted every other refueling outage interval. | |
| 111. If coating degradation is observed that required repair or replacement, or for newly installed | |
| : coatings, subsequent inspections should occur over the next two refueling outage intervals to establish a performance trend on the coatings.
| |
| ENCLOSURE c. All accessible internal surfaces for tanks and heat exchangers should be inspected. | | ENCLOSURE c. All accessible internal surfaces for tanks and heat exchangers should be inspected. |
| A representative sample of internally coated piping components not less than 73 1-foot axial length circumferential segments of piping or 50 percent of the total length of each coating material and environment combination should be inspected. | | A representative sample of internally coated piping components not less than 73 1-foot axial length circumferential segments of piping or 50 percent of the total length of each coating material and environment combination should be inspected. |
| : d. Coatings specialists and inspectors should be qualified in accordance with an ASTM International standard endorsed in RG 1.54, "Service Levell, II, and Ill Protective Coatings Applied to Nuclear Power Plants," | | : d. Coatings specialists and inspectors should be qualified in accordance with an ASTM International standard endorsed in RG 1.54, "Service Levell, II, and Ill Protective Coatings Applied to Nuclear Power Plants," including staff guidance associated with a particular standard. |
| including staff guidance associated with a particular standard. | | : e. Monitoring and trending should include pre-inspection reviews of previous inspection results. f. The acceptance criteria should include that indications of peeling and delamination are not acceptable. |
| : e. Monitoring and trending should include pre-inspection reviews of previous inspection results. | | Blistering can be evaluated by a coating specialist; however, physical testing should be conducted to ensure that the blister is completely surrounded by sound coating bonded to the surface. Request: If coatings have been installed on the internal surfaces of in-scope components (i.e., piping, piping subcomponents, heat exchangers, and tanks), state how loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage will be managed, including: |
| : f. The acceptance criteria should include that indications of peeling and delamination are not acceptable.
| |
| Blistering can be evaluated by a coating specialist; | |
| : however, physical testing should be conducted to ensure that the blister is completely surrounded by sound coating bonded to the surface.
| |
| Request: | |
| If coatings have been installed on the internal surfaces of in-scope components (i.e., piping, piping subcomponents, heat exchangers, and tanks), state how loss of coating integrity due to blistering, | |
| : cracking, flaking,
| |
| : peeling, or physical damage will be managed, including:
| |
| : a. for each installed coating application, whether installation records used to apply the coating included material manufacturer installation specifications | | : a. for each installed coating application, whether installation records used to apply the coating included material manufacturer installation specifications |
| : b. the inspection method c. the parameters to be inspected | | : b. the inspection method c. the parameters to be inspected |
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| : e. the extent of inspections and the basis for the extent of inspections if it is not consistent with. item c above f. the training and qualification of individuals involved in coating inspections | | : e. the extent of inspections and the basis for the extent of inspections if it is not consistent with. item c above f. the training and qualification of individuals involved in coating inspections |
| : g. how trending of coating degradation will be conducted | | : g. how trending of coating degradation will be conducted |
| : h. acceptance criteria | | : h. acceptance criteria 1. corrective actions for coatings that do not meet acceptance criteria the program(s) that wiH be augmented to include the above requirements If necessary, provide revisions to license renewal application Section 3 Table 2s, Appendix A, and Appendix B. |
| : 1. corrective actions for coatings that do not meet acceptance criteria the program(s) that wiH be augmented to include the above requirements If necessary, provide revisions to license renewal application Section 3 Table 2s, Appendix A, and Appendix B.
| |
| Letter to Raymond A Lieb from Juan Uribe dated November 26, 2013 | | Letter to Raymond A Lieb from Juan Uribe dated November 26, 2013 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
|
| |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) DISTRIBUTION: | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) DISTRIBUTION: |
| HARD COPY: DLR R/F E-MAIL: PUBLIC RidsNrrDirResource RidsNrrDirRpb1 Resource RidsNrrDtrRpb2 Resource RidsNrrDtrRer1 Resource RidsNrrDirRer2 Resource RidsNrrDirRerb Resource RidsNrrDirRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApta Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMaiiCenter Resource E. Keegan B Hams (OGC) E Brown J. Uribe}} | | HARD COPY: DLR R/F E-MAIL: PUBLIC RidsNrrDirResource RidsNrrDirRpb1 Resource RidsNrrDtrRpb2 Resource RidsNrrDtrRer1 Resource RidsNrrDirRer2 Resource RidsNrrDirRerb Resource RidsNrrDirRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApta Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMaiiCenter Resource E. Keegan B Hams (OGC) E Brown J. Uribe}} |
Letter Sequence RAI |
|---|
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
|
MONTHYEARML11126A0882008-01-12012 January 2008
Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501
Project stage: Other
ML11126A0902008-01-15015 January 2008
Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008
Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
ML11126A0682008-05-0505 May 2008
Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System.
Project stage: Other
ML11126A0652008-08-0606 August 2008
Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System.
Project stage: Other
ML11126A0592008-10-0909 October 2008
Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection.
Project stage: Other
ML11126A0632008-10-10010 October 2008
Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1.
Project stage: Other
ML11126A0702008-10-10010 October 2008
Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2.
Project stage: Other
ML11126A0742008-11-0606 November 2008
Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System.
Project stage: Other
ML11126A0832008-12-18018 December 2008
Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501
Project stage: Other
ML11126A0712009-04-0707 April 2009
Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems.
Project stage: Other
ML11126A0892009-04-0707 April 2009
Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System.
Project stage: Other
ML1024505652010-08-27027 August 2010
License Renewal Application and Ohio Coastal Management Program Consistency Certification
Project stage: Other
ML1104500462011-02-17017 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection
Project stage: RAI
ML11126A0792011-02-25025 February 2011
Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic.
Project stage: Other
ML1104205972011-02-28028 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4
Project stage: RAI
ML1106801722011-03-17017 March 2011
Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S
Project stage: RAI
ML1107007322011-03-18018 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3
Project stage: RAI
L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011
Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1
Project stage: Response to RAI
ML11068A0002011-03-21021 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640)
Project stage: RAI
L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review of the License Renewal Application
Project stage: Response to RAI
L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review License Renewal Application
Project stage: Response to RAI
ML1108206242011-03-30030 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640)
Project stage: RAI
ML1109002952011-03-31031 March 2011
Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station
Project stage: Approval
ML1108204902011-04-0505 April 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1
Project stage: RAI
ML11110A0932011-04-15015 April 2011
Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System
Project stage: Other
ML11110A1072011-04-15015 April 2011
Drawing No. M-045, Rev. 56, Chemical Addition Systems
Project stage: Other
ML11110A1062011-04-15015 April 2011
Drawing No. M-042C, Rev. 33, Sampling System Sh. 3
Project stage: Other
ML11110A1052011-04-15015 April 2011
Drawing No. M-040A, Rev. 76, Reactor Coolant System Details
Project stage: Other
ML11110A0952011-04-15015 April 2011
Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0942011-04-15015 April 2011
Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0922011-04-15015 April 2011
Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System
Project stage: Other
L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011
Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples
Project stage: Other
L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011
Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...
Project stage: Response to RAI
ML11110A0882011-04-15015 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal
Project stage: Response to RAI
ML11110A0912011-04-15015 April 2011
Drawing No. M-011, Rev. 61, Domestic Water System
Project stage: Other
ML11110A0892011-04-15015 April 2011
Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System
Project stage: Other
ML1110500912011-04-19019 April 2011
Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application
Project stage: Other
L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4
Project stage: Response to RAI
ML1109807182011-04-20020 April 2011
Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2
Project stage: RAI
ML11126A0362011-04-29029 April 2011
Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator.
Project stage: Other
ML11126A0352011-04-29029 April 2011
Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil.
Project stage: Other
ML11126A0342011-04-29029 April 2011
Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start.
Project stage: Other
ML11126A0332011-04-29029 April 2011
Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0322011-04-29029 April 2011
Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0262011-04-29029 April 2011
Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System
Project stage: Other
ML11126A0252011-04-29029 April 2011
Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System
Project stage: Other
ML11126A0242011-04-29029 April 2011
Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System
Project stage: Other
ML11126A0192011-04-29029 April 2011
Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1
Project stage: Other
ML11126A0452011-04-29029 April 2011
Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps.
Project stage: Other
2011-02-25
[Table View] |
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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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 26. 2013 Mr. Raymond A. Ueb, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North Slate Route 2 Oak Harbor, OH 43449
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)
Dear Mr. Lieb:
By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review. the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure.
Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov.
Docket No. 50-346
Enclosure:
As stated cc w/encl. Listserv Sincerely,
,/Juan Uribe, Project Manage;/*
Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation November 26, 2013 Mr. Raymond A. Ueb, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)
Dear Mr. Lieb:
By tetter dated August 27, 2010, FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure.
Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3809 or by e-mail at Juan.Uribe@nrc.gov.
Docket No. 50-346
Enclosure:
As stated cc w/encl: Listserv DISTRIBUTION See next page Sincerely, IRA Samuel DeJesus Cuadrado/
Juan Uribe, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation ADAMS Accession No *ML 13294A500
.. "concurred via email OFFICE LA:DLR/RPB2*
PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME I King JUri be YDiaz-Sanabria JUri be (SCuadrado for) DATE 11/25/13 11/25/13 11/26/13 11/26/13 OFFICIAL RECORD COPY RAI 3.0.3-3 DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION Issue: Loss of coating integrity for Service Levell II and Other coatings Industry operating experience (OE) indicates that degraded coatings have resulted in unanticipated or accelerated corrosion of the base metal and degraded performance of downstream equipment (e.g., reduction in flow, drop in pressure, reduction in heat transfer) due to flow blockage.
Based on these industry OE examples, the staff has questions related to how the aging effect, loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage, would be managed for Service Levellll and Other coatings.
For purposes of this request for additional information (RAI): a. Service Levell II coatings are those installed on the interior of in-scope piping, heat exchanges, and tanks which support functions identified under Title 10 of the Code of Federal Regulations (CFR) 54.4(a)(1) and (a)(2). b. "Other coatings," include coatings installed on the interior of in-scope piping, heat exchangers, and tanks whose failure could prevent satisfactory accomplishment of any of the functions identilied under 10 CFR 54.4(a)(3).
- c. The term "coating" includes morganic (e.g., zinc-based) or organic (e.g., elastomeric or polymeric) coatings, linings (e.g., rubber, cementitious), and concrete surfacers that are designed to adhere to a component to protect its surface. d. The terms "paint" and "linings" should be considered as coatings.
The staff believes that to effectively manage loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage of Service Levell II and Other coatings an aging management program should include: a. Baseline visual inspections of coatings installed on the interior surfaces of in-scope components should be conducted in the 1 0-year period prior to the period of extended operation
- b. Subsequent periodic inspections where the interval is based on the baseline inspection results. For example: 1. If no peeling, delamination, blisters, or rusting are observed, and any cracking and flaking have been found acceptable, subsequent inspections could be conducted after multiple refueling outage intervals (e.g., for example six years, or more if the same coatings are in redundant trains}. ii. If the inspection results do not meet the above; but, a coating specialist has determined that no remediation is required, subsequent inspections could be conducted every other refueling outage interval.
111. If coating degradation is observed that required repair or replacement, or for newly installed coatings, subsequent inspections should occur over the next two refueling outage intervals to establish a performance trend on the coatings.
ENCLOSURE c. All accessible internal surfaces for tanks and heat exchangers should be inspected.
A representative sample of internally coated piping components not less than 73 1-foot axial length circumferential segments of piping or 50 percent of the total length of each coating material and environment combination should be inspected.
- d. Coatings specialists and inspectors should be qualified in accordance with an ASTM International standard endorsed in RG 1.54, "Service Levell, II, and Ill Protective Coatings Applied to Nuclear Power Plants," including staff guidance associated with a particular standard.
- e. Monitoring and trending should include pre-inspection reviews of previous inspection results. f. The acceptance criteria should include that indications of peeling and delamination are not acceptable.
Blistering can be evaluated by a coating specialist; however, physical testing should be conducted to ensure that the blister is completely surrounded by sound coating bonded to the surface. Request: If coatings have been installed on the internal surfaces of in-scope components (i.e., piping, piping subcomponents, heat exchangers, and tanks), state how loss of coating integrity due to blistering, cracking, flaking, peeling, or physical damage will be managed, including:
- a. for each installed coating application, whether installation records used to apply the coating included material manufacturer installation specifications
- b. the inspection method c. the parameters to be inspected
- d. when inspections will commence and the frequency of subsequent inspections
- e. the extent of inspections and the basis for the extent of inspections if it is not consistent with. item c above f. the training and qualification of individuals involved in coating inspections
- g. how trending of coating degradation will be conducted
- h. acceptance criteria 1. corrective actions for coatings that do not meet acceptance criteria the program(s) that wiH be augmented to include the above requirements If necessary, provide revisions to license renewal application Section 3 Table 2s, Appendix A, and Appendix B.
Letter to Raymond A Lieb from Juan Uribe dated November 26, 2013
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640) DISTRIBUTION:
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