ML12157A238
| ML12157A238 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/22/2012 |
| From: | Harris B License Renewal Projects Branch 1 |
| To: | FirstEnergy Nuclear Operating Co |
| Harris B 301-415-2277 | |
| References | |
| TAC ME4640 | |
| Download: ML12157A238 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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June 22,2012
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LICENSEE:
FirstEnergy Nuclear Operating Company FACILITY:
Davis-Besse Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON APRIL 26,2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE DAVIS-BESSE NUCLEAR POWER STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME4640)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company (FENOC or the applicant) held a telephone conference call on April 26, 2012, to discuss and clarify the staff's requests for additional information (RAls) concerning the Davis-Besse Nuclear Power Station license renewal application. provides a listing of the participants and Enclosure 2 contains a description of the staff's concerns discussed with the applicant A brief description on the status of the items is also included.
The applicant had an opportunity to comment on this sum Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: Listserv
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS April 26, 2012 PARTICIPANTS AFFILIATIONS Samuel Cuadrado de Jesus Allen Hiser Christopher Sydnor Jeffrey Poehler Steve Dort Larry Hinkle Ashok Nana Mark Rinckel Sarah Davidsaver David Noxon U.S. Nuclear Regulatory Commission (NRC)
NRC NRC
!\\IRC FirstEnergy Nuclear Operating Company (FENOC)
FENOC FENOC FENOC FENOC FENOC ENCLOSURE 1
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE LICENSE RENEWAL APPLICATION April 26, 2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company (FENOC or the applicant) held a telephone conference call on April 26, 2012, to discuss and clarify the following requests for additional information (RAls) concerning the Davis-Besse license renewal application (LRA).
RAI 4.2.2-4 Reactor Vessel Upper-Shelf Energy Evaluations Discussion:
The staff discussed RAI 4.2.2-4 with the applicant. The applicant requested clarification on the options to demonstrate an acceptable upper-shelf energy (USE) for the beltline materials. After some discussion, the applicant indicated that the reactor vessel equivalent margin analysis (EMA) option would be used to demonstrate an acceptable USE for the Linde 80 welds. The applicant stated that the EMA for weld WF-182-1 results were previously provided in LRA Section 4.2.2.3. The applicant also stated that the EMA for weld WF-182-1 bounds the she" welds. For the remaining Linde 80 welds, reactor vessel inlet/outlet nozzle welds, the applicant indicated that an EMA had been performed for the outlet nozzle welds and that this analYSis is bounding for the nozzle welds. As part of the RAI response, the applicant agreed to submit the outlet nozzle weld EMA. Also, the applicant agreed to provide a technical justification as to why the EMA for weld WF-182-1 bounds the she" welds and the EMA for the outlet nozzle welds bounds the nozzle welds. These technical justifications are to include addressing geometry differences.
RAI4.2.4-1 Pressure-Temperature Limits Discussion:
For RAI 4.2.4-1, the staff provided clarification that this RAI pertains not only to reactor vessel beltline materials but also to a" the other ferritic reactor coolant pressure boundary (RCPB) materials. The applicant stated that the methodology used to develop the pressure temperature (P-T) limit curves, considered a" ferritic RCPB materials and is documented in topical report BAW-10046A, "Methods of Compliance with Fracture Toughness and Operational Requirements for 10 CFR 50 Appendix G," Revision 2. This topical report was approved by the NRC in a Safety Evaluation Report dated April 30, 1986.
The staff stated that the information provided by the applicant was understood and that the telephone conference call was productive.
There was no further discussion and the call was concluded.
ENCLOSURE 2
. ML12157a238 OFFICE LA:RPB'I:DLR PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1 :DLR NAME IKing BHarris I D Morey BHarris DATE 06/14/12 06/15/12 06/21/12 06/22/12