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FENOCT%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 November 21, 2014 L-14-305 10 CFR 50.71(e)10 CFR 50.54(a)ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Submittal of the Updated Final Safety Analysis Report, Revision 30 In accordance with the requirements of 10 CFR 50.71(e), the FirstEnergy Nuclear Operating Company (FENOC) is hereby submitting to the Nuclear Regulatory Commission (NRC) the Davis-Besse Nuclear Power Station (DBNPS) Updated Final Safety Analysis Report (UFSAR) Revision 30 in CD-ROM format. This submittal reflects facility and procedure changes implemented between June 13, 2012 (the end of Refueling Outage 17), and May 8, 2014 (the end of Refueling Outage 18), along with several changes implemented after Refueling Outage 18.This UFSAR revision is the first to be submitted for DBNPS in CD-ROM format. To support this transition, the entire text of the UFSAR and Fire Hazards Analysis Report (FHAR) was retyped. In accordance with 10 CFR 50.71(e)(5), a change indicator (revision bar) was only used where actual changes to UFSAR and FHAR text were incorporated.
All retyped pages were provided with a page change identification (date of change).In accordance with NRC guidance for electronic submissions, Attachment 1 provides a listing of the document components that comprise the enclosed CD-ROM. In addition to the UFSAR, the submission includes documents incorporated by reference in the UFSAR updated during the aforementioned time. These documents include the DBNPS FHAR, Revision 26, the Technical Requirements Manual (TRM), Revision 14, and updated drawings.The Technical Specification (TS) Bases, Revision 20, are submitted in accordance with Technical Specification 5.5.13.d, "Technical Specifications (TS) Bases Control Program."
Davis-Besse Nuclear Power Station L-14-305 Page 2 In accordance with 10 CFR 50.54(a), FENOC is hereby submitting a copy of the current revision of the FENOC Quality Assurance Program Manual (QAPM). The QAPM, Revision 19, is included in the enclosed CD-ROM.Attachment 2 includes a summary of information removed from the DBNPS UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1.In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," as endorsed by NRC Regulatory Issue Summary (RIS) 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," a summary of regulatory commitment changes is provided in Attachment 3.This certifies, to the best of my judgment and belief, that Revision 30 of the DBNPS UFSAR accurately presents changes made since the previous submittal that are necessary to reflect information and analysis submitted to the Commission or pursuant to Commission requirements.
This letter contains no new regulatory commitments.
If you have any questions regarding this report, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing, at 330-315-6810.
Sincerely, Raymond A. Lieb Attachments:
- 1. Document Components on CD-ROM 2. Information Removed from the DBNPS UFSAR 3. Commitment Change Summary Report
Enclosures:
DBNPS UFSAR, FHAR, TRM, TS Bases, FENOC QAPM, and other updated documents incorporated by reference (on CD-ROM)cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board (without Enclosures)
Attachment 1 L-14-305 Document Components on CD-ROM Page 1 of 2 File Name Size 001 UFSAR List of Effective Pages Rev 30.pdf 002 UFSAR Section 1.pdf 003 UFSAR Section 2.pdf 004 UFSAR Section 3.pdf 005 UFSAR Section 4.pdf 006 UFSAR Section 5.pdf 007 UFSAR Section 6.pdf 008 UFSAR Section 7.pdf 009 UFSAR Section 8.pdf 010 UFSAR Section 9.pdf 011 UFSAR Section 10.pdf 012 UFSAR Section 11 .pdf 013 UFSAR Section 12.pdf 014 UFSAR Section 13.pdf 015 UFSAR Section 14.pdf 016 UFSAR Section 15.pdf 017 UFSAR Section 16.pdf 018 UFSAR Section 17.pdf 019 FHAR List of Effective Pages Rev 26.pdf 020 FHAR Section l.pdf 021 FHAR Section 2.pdf 022 FHAR Section 3.pdf 023 FHAR Section 4 Part 1 of 2.pdf 024 FHAR Section 4 Part 2 of 2.pdf 025 FHAR Section 5.pdf 026 FHAR Section 6.pdf 027 FHAR Section 7.pdf 028 FHAR Section 8.pdf 029 FHAR Section 9.pdf 030 FHAR Appendix A.pdf 031 FHAR Appendix B-i .pdf 032 FHAR Appendix B-2.pdf 033 FHAR Appendix C-i .pdf 034 FHAR Appendix C-2.pdf 035 FHAR Appendix C-3.pdf 036 FHAR Appendix D.pdf 037 FHAR Appendix E.pdf 038 TRM Rev 14.pdf 039 TS Bases Rev 20.pdf 040 FENOC QAPM Rev 19.pdf 041 DWG E-0030B Sht 0016C Rev 2.pdf 042 DWG E-0030B Sht 0016D Rev 2.pdf 043 DWG E-030-00028 Rev 15.pdf 044 DWG E-030AQ-00006 Rev 6.pdf 045 DWG E-030AQ-00012 Rev 3.pdf 87 KB 3,622 KB 17,219 KB 33,157 KB 4,048 KB 1, 541 KB 4,566 KB 5,022 KB 11,955 KB 11,141 KB 2,636 KB 1,923 KB 10,948 KB 115 KB 534 KB 1,858 KB 41 KB 40 KB 85 KB 125 KB 72 KB 172 KB 37,494 KB 35,276 KB 88 KB 81 KB 71 KB 165 KB 203 KB 3,313 KB 22,413 KB 28,612 KB 643 KB 1,597 KB 2,300 KB 301 KB 63 KB 1,070 KB 2,292 KB 4,153 KB 292 KB 278 KB 2,026 KB 990 KB 1,551 KB Attachment 1 L-14-305 Page 2 of 2 File Name Size 046 DWG E-030AQ-00036 Rev 2.pdf 284 KB 047 DWG E-0031 B Index Sht 0002 Rev 34.pdf 239 KB 048 DWG E-0031B Sht 0003 Rev 15.pdf 244 KB 049 DWG E-0031 B Sht 0003A Rev 3.pdf 197 KB 050 DWG E-0031B Sht 0008 Rev 12.pdf 291 KB 051 DWG E-0031B Sht 0009 Rev 16.pdf 312 KB 052 DWG E-0031B Sht 0012 Rev 9.pdf 294 KB 053 DWG E-0044B Sht 0005 Rev 12.pdf 317 KB 054 DWG E-0044B Sht 0014B Rev 11 .pdf 178 KB 055 DWG E-0046B Index Sht 0003 Rev 95.pdf 262 KB 056 DWG E-0048B Sht 0007B Rev l.pdf 241 KB 057 DWG E-0048B Sht 001 lC Rev 11.pdf 222 KB 058 DWG E-0048B Sht 0013 Rev 8.pdf 264 KB 059 DWG E-0048B Sht 0033A Rev 7.pdf 222 KB 060 DWG E-0048B Sht 0033C Rev 6.pdf 224 KB 061 DWG E-0050B Sht 0004C Rev 10.pdf 269 KB 062 DWG E-0050B Sht 0015A Rev 5.pdf 259 KB 063 DWG E-0052B Sht 0021A Rev 12.pdf 420 KB 064 DWG E-0052B Sht 0021 B Rev 6.pdf 220 KB 065 DWG E-0052B Sht 0045A Rev 9.pdf 351 KB 066 DWG E-0060B Index Sht 0002 Rev 71 .pdf 339 KB 067 DWG E-0060B Sht 0014D Rev 6.pdf 228 KB 068 DWG M-536-00035 Rev 9.pdf 204 KB 069 DWG M-536-00045 Rev 9.pdf 211 KB 070 DWG M-536-00055 Rev 11 .pdf 204 KB 071 DWG M-536-00075 Rev 11.pdf 208 KB 072 DWG M-0567 Rev 30.pdf 515 KB 073 DWG M-0568 Rev 46.pdf 420 KB Attachment 2 L-14-305 Information Removed from DBNPS UFSAR Page 1 of 1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees report a brief description of information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides a summary of the information removed from the UFSAR and the basis for removal.1. Removed two references from Section 6.5. As discussed in Section 6.2.1.3.2, the containment response analysis is documented by another reference, which superseded these two references.
The removed references are not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance with relevant regulatory and industry standards.
- 2. Removed depiction of an abandoned position switch from Figure 5.1-2. The abandoned position switch is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.
- 3. Removed the specific percentage of reactor full power corresponding to the steam generator low level limit from Section 15.2.7. The replacement of the steam generators modified the low level limit. The pertinent information for the accident analysis is the concept of the steam generator low level limit, which remains in the UFSAR. The specific percentage of reactor full power is information not necessary to understand the accident analysis.
Attachment 3 L-14-305 Commitment Change Summary Report October 2012 -September 2014 Page 1 of 1 COMMITMENT NUMBER /SOURCE IDATE COMMITMENT DESCRIPTION CHANGE REASON FOR CHANGE DB-004848 Serial 1161 06/24/85 In response to NRC GL 85-02 regarding SG tube integrity issues and SG tube rupture mitigation, a description of the DBNPS V&LPM system was provided and captured as a regulatory commitment.
Commitment closed.In September 1988, the NRC issued NUREG-0844 documenting the resolution of SG tube integrity issues. It was concluded that a loose parts monitoring system may only provide a small additional incremental benefit in preventing SG tube ruptures.
Given the implementation of secondary-side visual inspections, there was insufficient justification to support implementation of such a system.DBNPS provided relevant information regarding its V&LPM system, but did not specifically establish a commitment to maintain this system to meet a regulatory requirement.
This information no longer fits the definition of a regulatory commitment and tracking it as such is not necessary.
List of Abbreviations Used DBNPS GL NRC SG V&LPM Davis-Besse Nuclear Power Station Generic Letter Nuclear Regulatory Commission Steam Generator Vibration and Loose Parts Monitoring