Letter Sequence Other |
|---|
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
Withhold in accordance with 10 CFR 2.390 Upon removal of Enclosure E, this letter can be decontrolled.
~5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Raymond A. Lieb 419-321-7676 Vice President, Nuclear Fax: 419-321-7582 April 21, 2015 L-15-139 10 CFR 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 License Renewal Reactor Vessel Internals Inspection Plan (TAC No. ME4640)
By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), 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, Unit No. 1 (Davis-Besse). In the Nuclear Regulatory Commission (NRC) Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station dated September 2013 (ML13248A267),
Appendix A, "Davis-Besse Nuclear Power Station License Renewal Commitments,"
Table A-i, "Davis-Besse License Renewal Commitments," Commitment No. 15, FENOC committed to the following:
"In association with the PWR Reactor Vessel Internals Program, a plant-specific inspection plan for ensuring the implementation of MRP-227 program guidelines, as amended by the safety evaluation for MRP-227, and Davis-Besse's responses to the plant-specific action items, as identified in Section 4.2 of the safety evaluation for MRP-227, will be submitted for NRC review and approval.
- NOTE: The inspection plan will be submitted no later than 2 years after issuance of the renewed operating license or 2 years prior to the beginning of the period of extended operation (April 22, 2015), whichever is earlier."
The renewed operating license for Davis-Besse has not been issued. The period of extended operation begins April 22, 2017. Accordingly, attached is the requested plant-specific inspection plan, which is being submitted not less than 24 months before entering the period of extended operation.
Davis-Besse Nuclear Power Station, Unit No. 1 L-15-139 Page 2 The Enclosures listed below provide the Davis-Besse Reactor Vessel Internals Inspection Plan and related supporting reports, developed by AREVA NP Inc.
(AREVA NP) and required by MRP-227-A:
A. AREVA NP Licensing Report No. ANP-3290 Revision 1, "Reactor Vessel Internals Inspection Plan for the Davis-Besse Nuclear Power Plant Unit No. 1" B. AREVA NP Report No. ANP-3285 Revision 0, "Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld" C. AREVA NP Report No. ANP-3359NP Revision 0, "Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison" (Non-Proprietary)
D. AREVA NP Affidavit to Support the Disclosure Request for the Proprietary Assessment Report E. AREVA NP Report No. ANP-3359P Revision 0, "Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison" (Proprietary)
AREVA NP Report No. ANP-3359P (Enclosure E) documents Davis-Besse reactor vessel internals details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure C. Upon removal of Enclosure E, this letter can be decontrolled.
The Attachment identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse) in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC; they are described only as information and are not Regulatory Commitments. Please notify Mr. Trent A. Henline, Supervisor, Nuclear Engineering Programs, at (419) 321-7824 of any questions regarding this document or associated Regulatory Commitments.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 21I*,2015.
Davis-Besse Nuclear Power Station, Unit No. 1 L-15-139 Page 3 Attachments:
Regulatory Commitment List
Enclosures:
A.
AREVA NP Licensing Report No. ANP-3290 Revision 1, "Reactor Vessel Internals Inspection Plan for the Davis-Besse Nuclear Power Plant Unit No. 1" B.
AREVA NP Report No. ANP-3285 Revision 0, "Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld" C.
AREVA NP Report No. ANP-3359NP Revision 0, "Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison" (Non-Proprietary)
D.
AREVA NP Affidavit to Support the Disclosure Request for the Proprietary Assessment Report E.
AREVA NP Report No. ANP-3359P Revision 0, "Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison" (Proprietary) cc:
NRC DLR Project Manager NRC Region III Administrator cc:
w/o Attachment or Enclosures NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board
Attachment L-15-139 Regulatory Commitment List Page 1 of 2 The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse) in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC; they are described only as information and are not Regulatory Commitments. Please notify Mr. Trent A. Henline, Supervisor, Nuclear Engineering Programs, at (419) 321-7824 of any questions regarding this document or associated Regulatory Commitments.
Regulatory Commitment Due Date
- 1. In response to MRP-227-A Applicant/Licensee Within one year of the Action Item 6, submit detailed analyses justifying detection of degradation the acceptability of inaccessible and exceeding the non-inspectable component items (core barrel acceptance criteria of cylinder including vertical and circumferential the linked MRP-227-A seam welds, former plates, external baffle-to-primary component baffle bolts and their locking devices, core barrel-items leading to to-former bolts and their locking devices, and expansion internal baffle-to-baffle bolts) for continued operation through the period of extended operation by performing an evaluation or by proposing a schedule for replacement of the component items (see CR 2014-06427).
- 2. In response to MRP-227-A Applicant/Licensee One year prior to the Action Item 7, develop and submit a plant-specific MRP-227-A analysis to demonstrate that the Incore inspection of the Monitoring Instrumentation (IMI) guide tube applicable component assembly spiders, Control Rod Guide Tube items (CRGT) spacer castings, and additional RV Internals component items that may be fabricated from CASS, martensitic stainless steel, or martensitic precipitation-hardened stainless steel materials (e.g., Core Support Shield (CSS) vent valve top and bottom retaining rings) will maintain their functionality during the period of extended
Attachment L-15-139 Page 2 of 2 operation. The analysis will consider the possible loss of fracture toughness in these component items due to thermal embrittlement (TE) and/or irradiation embrittlement (IE) and may also need to consider limitations on accessibility for inspection and the resolution/sensitivity of the inspection techniques. The Davis-Besse analysis will be consistent with the licensing basis and the need to maintain the functionality of the component items being evaluated under all licensing basis conditions of operation.
- 3. In response to MRP-227-A Applicant/Licensee Action Item 8, update and submit an evaluation for the period of extended operation regarding the effect of irradiation on the mechanical properties and deformation limits of the RV internals that was evaluated for the current term of operation in Appendix E of Topical Report BAW-10008, Part 1, Revision 1 supplemented by DB-1 USAR Appendix 4A.
April 22, 2017
