Letter Sequence RAI |
|---|
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
- Approval, Approval, 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-12-341, Firstenergy Nuclear Operating Cos Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), 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, 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
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MONTHYEARML11126A0842003-01-22022 January 2003
Drawing No. LR-M039A, Revision 3, Piping & Instrument Diagram Miscellaneous Liquid Radioactive Waste. Job Code 12501
Project stage: Other
ML11126A0762003-01-22022 January 2003
Drawing No. LR-M047, Revision 1, Piping & Instrument Diagram Radwaste Drumming Station
Project stage: Other
ML11126A0552003-08-12012 August 2003
Drawing No. LR-M030B, Revision 1, Reactor Coolant System Instrumentation
Project stage: Other
ML11126A0862005-08-23023 August 2005
Drawing No. LR-M040D, Revision 2, Piping & Instrument Diagram Reactor Coolant Pump & Motor. Job Code 12501
Project stage: Other
ML11126A0882008-01-12012 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 Systems2008-01-15015 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
ML1104500462011-02-17017 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection
Project stage: RAI
L-11-037, Independent Spent Fuel Storage Installation - Changes, Tests, and Experiments2011-02-17017 February 2011
Independent Spent Fuel Storage Installation - Changes, Tests, and Experiments
Project stage: Request
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
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
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
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
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
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
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
ML11110A0892011-04-15015 April 2011
Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System
Project stage: Other
ML11110A0912011-04-15015 April 2011
Drawing No. M-011, Rev. 61, Domestic Water System
Project stage: Other
ML11110A0922011-04-15015 April 2011
Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System
Project stage: Other
ML11110A0932011-04-15015 April 2011
Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System
Project stage: Other
ML11110A0942011-04-15015 April 2011
Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0952011-04-15015 April 2011
Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A1052011-04-15015 April 2011
Drawing No. M-040A, Rev. 76, Reactor Coolant System Details
Project stage: Other
ML11110A1062011-04-15015 April 2011
Drawing No. M-042C, Rev. 33, Sampling System Sh. 3
Project stage: Other
ML11110A1072011-04-15015 April 2011
Drawing No. M-045, Rev. 56, Chemical Addition Systems
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
ML1109807182011-04-20020 April 2011
Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2
Project stage: RAI
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
ML11126A0342011-04-29029 April 2011
Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start
Project stage: Other
ML11126A0172011-04-29029 April 2011
Drawing No. LR-M006E, Revision 1, Piping & Instrument Diagram Condensate System
Project stage: Other
ML11126A0182011-04-29029 April 2011
Drawing No. LR-M007A, Revision 1, Piping & Instrument Diagram Steam Generator Secondary 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
ML11126A0202011-04-29029 April 2011
Drawing No. LR-M003B, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 2
Project stage: Other
ML11126A0212011-04-29029 April 2011
Drawing No. LR-M003C, Revision 2, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 3
Project stage: Other
2011-02-17
[Table View] |
Text
Projects Branch 1 Division of License Renewal UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 14, 2012 Mr. Raymond A. Lieb, 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 RELATED TO HIGH STRENGTH BOLTING (TAC NO. ME4640)
Dear Mr. Lieb:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company 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 (NRC or the staff) 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 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel. CuadradoDeJesus@nrc.gov.
Sincerely, elcu~<2:er Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Requests for additional information cc w/encl: Listserv
DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO HIGH STRENGTH BOLTING RAI B.2.4-1 a
Background:
The November 2,2012, supplemental response to request for additional information (RAI) B.2.4-1 states that American Society of Testing and Materials (ASTM) A-540 bolts are used in structural applications. The response classified ASTM A-325 and A-490 structural bolts as high strength. However, depending on the grade and class of ASTM A-540 bolts, the minimum specified yield strength of the material is specified as 130,140, or 150 kilo-pounds per square inch (ksi). NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," aging management program (AMP) XI.M18 states, "[p]reventive measures also include using bolting material that has an actual measured yield strength limited to less than 1,034 megapascals (MPa) (150 kilo-pounds per square inch [ksi])." Given the variability in actual yield strength supplied by a material manufacturer, it is possible that some in-service ASTM A-540 bolts should be classified as high strength. GALL Report AMP XI.M18 further states that, "[h]igh strength closure bolting (actual yield strength greater than or equal to 1,034 MPa [150 ksi]), if used, should be monitored for cracking."
The original response to RAI B.2.4-1, provided on May 24, 2011, which stated, "[v]isual examinations of structural assemblies will detect corrosion or conditions indicative of a corrosive environment that could lead to stress corrosion cracking (SCC) in potentially susceptible high strength bolting, and will cause appropriate corrective action to be taken under the Corrective Action Program when necessary," is still applicable if there are high strength ASTM A-540 bolts.
Issue:
The staff lacks sufficient information to determine which ASTM A-540 grade and class materials were used; if grade and class materials were used that have a minimum specified yield equal to or higher than 130 ksi; the actual measured yield strength of inservice bolts; if none of the currently installed bolts are high strength bolts; what controls will be in place to ensure that the actual measured yield strengths of ASTM A-540 supplied replacements will not exceed 150 ksi; and what inspections will be conducted for these high strength bolts.
In addition, if visual examinations will be used to detect corrosion or conditions indicative of a corrosive environment that could lead to SCC, it is unclear how a corrosive environment is defined at Davis-Besse Nuclear Power Station (Davis-Besse), and how a non-corrosive environment can be guaranteed to be maintained throughout the period of extended operation.
ENCLOSURE
- 2 Request:
The staff requests the applicant state the following:
a) The ASTM A-540 grade and class of materials that are used in in-scope structural locations b) If grade and class materials were used that have a minimum specified yield equal to or higher than 130 ksi, the actual measured yield strength of in-service bolts c) If none of the currently installed bolts are high strength bolts, what controls will be in place to ensure that the actual measured yield strengths of A-540 supplied replacements will not exceed 150 ksi d) If high strength ASTM A-540 bolting material has been used in in-scope structural applications, what inspections will be conducted e) If visual examinations will be used to detect corrosion or conditions indicative of a corrosive environment in lieu of volumetric or surface (for removed bolts) examinations to detect SCC, the definition for a corrosive environment at Davis-Besse, and the threshold for which an environment will be classified as corrosive f) How it will be demonstrated that a non-corrosive environment is maintained for all high strength bolts, and how visual inspections will be able to detect all instances of corrosion or a corrosive environment, or update the AMP to show that volumetric examinations comparable to that of American Society of Mechanical Engineers Code Section XI, Table IWB-2500-1, Examination Category BG-1 are being performed on high strength bolting
November 14, 2012 Mr. Raymond A. Lieb, 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 RELATED TO HIGH STRENGTH BOLTING (TAC NO. ME4640)
Dear Mr. Lieb:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company 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 (NRC or the staff) 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 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel. CuadradoDeJesus@nrc.gov.
Sincerely, IRA!
Samuel Cuadrado De Jesus, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Requests for additional information cc w/encl: Listserv DISTRIBUTION:
See next page ADAMS Accession No.:ML12318A246
- concurrence via email OFFICE PM:DLR/RPB1 LA:DLRlRPB2*
BC:DLR/RPB1 PM:DLRlRPB1 NAME SCuadrado IKing DMorey SCuadrado DATE 11114/12 11/13/12 11/14/12 11/14/12 OFFICIAL RECORD COpy
Letter to Raymond A. Ueb from Samuel Cuadrado De Jesus dated November 14, 2012
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION RELATED TO HIGH STRENGTH BOLTING (TAC NO. ME4640)
DISTRIBUTION:
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