ML15307A191
| ML15307A191 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/01/2015 |
| From: | Mccree V NRC/EDO |
| To: | John Stetkar Advisory Committee on Reactor Safeguards |
| R. Plasse, NRR/DLR, 301-415-1427 | |
| Shared Package | |
| ML15307A154 | List: |
| References | |
| LTR-15-0568-1 | |
| Download: ML15307A191 (3) | |
Text
J. Stetka UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 1, 2015 John W. Stetkar, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1
Dear Mr. Stetkar:
During the 629th meeting of the Advisory Committee on Reactor Safeguards (ACRS) held November 4-7, 2015, the Committee completed its review of the license renewal application (LRA) for Davis-Besse Nuclear Power Station, Unit 1. The Committee also reviewed the U.S.
Nuclear Regulatory Commission (NRC) staffs associated final safety evaluation report for this application.
The NRC staff appreciates the Committees objective and in-depth review of the Davis-Besse license renewal application and final safety evaluation report under the requirements of 10 CFR Part 54, Requirements for Renewal of Operating License for Nuclear Power Plants.
In the Committees final report (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15316A125), dated November 12, 2015, it concurred with the NRC staffs conclusion on the Davis-Besse, Unit 1 license renewal. Both the Committee and the NRC staff believe that the licensee, FirstEnergy Nuclear Operating Company (FENOC), has demonstrated that it will adequately manage the effects of aging and maintain intended functions consistent with the current licensing basis for the period of extended operation (as required by 10 CFR 54.21(a)(3)). The Committee further concurs with the NRC staff that there are no open license renewal issues related to 10 CFR 54.29(a)(1) or 10 CFR 54.29(a)(2) that would prevent the NRC from renewing the Davis-Besse operating license.
In accordance with the Atomic Energy Act of 1954, as amended, the Committee has statutory responsibilities to review and advise the Commission on the licensing and operation of production and utilization facilities and related safety issues. Under this statutory authority, the Committee conducted a thorough and in-depth review of the methodologies that FENOC used to analyze cracking effects that could impact the intended design function of the shield building under design basis loadings, including seismic events. Based on its independent review, the Committee concluded on the basis of the results of the analysis methodologies used by FENOC that adequate margin exists such that the shield building remains capable of performing its intended functions. The staff position is consistent with this conclusion (as documented in Inspection Reports (IR) 05000346/2012009 and 05000346/2014008). The Committee further indicated that the shield building monitoring aging management program, as described in LRA Amendment No. 60, is sufficient to prevent loss of intended functions due to potential growth of
the shield building cracking effects in accordance with the current licensing basis for the period of extended operation. In its final report, the Committee expressed the importance of the NRC staffs review and approval of the methodologies used to analyze the effects of concrete cracking in the shield building (cracking effects analysis methodologies) as an amendment to Davis-Besses current license. The staff agrees with the importance of addressing this current licensing basis issue related to laminar cracking of the shield building under 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, and notes that the cracking effects analysis issue is currently being addressed by the staff under the NRC Enforcement Policy.
Specifically, the staff issued a Severity Level IV non-cited violation of 10 CFR 50.59(c)(2) and an associated Green finding in IR 05000346/2014008 (ADAMS Accession No. ML15148A489) in May 2015 for FENOCs failure to request and obtain a license amendment under the regulations of 10 CFR 50.90. At this time, FENOC is expected to submit a license amendment to address this issue. However, the staff review of an amendment to the license addressing cracking effects analysis methodologies may not be completed prior to commencement of the period of extended operation. Since it is a current operating issue, review and approval of the cracking effects analysis methodologies will be conducted by staff as part of normal licensing activity under 10 CFR Part 50 and corrective action for the violation is to be reviewed by inspectors as part of the Reactor Oversight Program. Therefore, addressing these current operational activities does not preclude license renewal, and the staff is not conditioning the license renewal as suggested in item two of the Committees final letter.
The NRC staff acknowledged the insights provided by the ACRS during the Subcommittee Meeting held on September 23, 2015, regarding recommended improvements to the Davis-Besse shield building monitoring program. On October 6, 2015, FENOC submitted revisions to the shield building monitoring program. The revisions, evaluated by the staff, include enhancements to the method of monitoring the areal extent of laminar cracking to require impulse response mapping, in addition to visual inspections of the cracks themselves using core bores perpendicular to the building exterior wall.
The NRC staff recognizes and appreciates the Committees commitment to safety and appreciates its continued support of the license renewal process.
Sincerely,
/RA/
Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY
ML15148A489) in May 2015, for FENOCs failure to request and obtain a license amendment under the regulations of 10 CFR 50.90. At this time, FENOC is expected to submit a license amendment to address this issue. However, the staff review of an amendment to the license addressing cracking effects analysis methodologies may not be completed prior to commencement of the period of extended operation. Since it is a current operating issue, review and approval of the cracking effects analysis methodologies will be conducted by staff as part of normal licensing activity under 10 CFR Part 50 and corrective action for the violation is to be reviewed by inspectors as part of the Reactor Oversight Program. Therefore, addressing these current operational activities does not preclude license renewal, and the staff is not conditioning the license renewal as suggested in item two of the Committees final letter.
The NRC staff acknowledged the insights provided by the ACRS during the Subcommittee Meeting held on September 23, 2015, regarding recommended improvements to the Davis-Besse shield building monitoring program. On October 6, 2015, FENOC submitted revisions to the shield building monitoring program. The revisions, evaluated by the staff, include enhancements to the method of monitoring the areal extent of laminar cracking to require impulse response mapping, in addition to visual inspections of the cracks themselves using core bores perpendicular to the building exterior wall.
The NRC staff recognizes and appreciates the Committees commitment to safety and appreciates its continued support of the license renewal process.
Sincerely,
/RA/
Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY DISTRIBUTION: LTR-15-0568-1 See next page ADAMS Accession Nos. ML15307A154 (Package); ML15316A125 (Incoming); ML15307A191 (Outgoing)
- concurred via e-mail OFFICE LA:DLR PM: RPB1:DLR Tech Editor
NAME YEdmonds RPlasse CHsu w/edits EWilliamson DATE 11/ 13 /2015 11 / 10 /2015 11/10 /2015 11/ 17 /2015 OFFICE BC: RPB1:DLR D:DLR:NRR D:NRR EDO NAME YDiaz-Sanabria C.Miller WDean VMcCree DATE 11/ 17 /2015 11/ 19 /2015 11/ 26/2015 12/1 /2015
Letter to J. Stetkar from V. McCree dated December X, 2015 DISTRIBUTION: LTR-15-0568 PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsEdoMailCenter Resource RidsNrrMailCenter Resource RidsNrrOd Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR R. Plasse P. Clark B. Purnell, DORL R. Haskell, DORL J. Poole, DORL S. Burnell, OPA I. Couret, OPA D. McIntyre, OPA K. Kanatas, OGC B. Harris, OGC V. Mitlyng, RIII P. Chandrathil, RIII D. Kimble, Davis-Besse Station, RIII J. Cameron, RIII J. Rutkowski, RIII B. Bartlett, RIII B. Boston, RIII