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May 5, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-i 8 NRC Docket No. 50-244
Subject:
Submittal of Revision 26 to the Updated Final Safety Analysis Report and Revision *12 of the Fire Protection Program
!n accordance with 10 CFR 50.71(e} and 10 CFR 50.4(b)(6}, enclosed is Revision 26 of the Updated Final Safety Analysis Report (UFSAA) and Revision i2 of the Fire Protection Program (FPP) for R.E. Ginna Nuclear Power Plant (Ginna) (Enclosure 1). The enclosed UFSAR Revision 26 and FPP Revision i 2 are being provided to the NRC in electronic format on CD-ROM and are being submitted ln its entirety, constituting a total replacement copy.
Additionally, Enclosure 2 contains supporting reference drawings for Revision 26 of the UFSAR in electronic format on CD~ROM.
10 CFR 50.71(e)(4) stipulates subsequent revisions must be filed annually or 6 months after each refueling outage provided the interval between successive updates does not exceed 24 months; the revisions must reflect all changes up to a maximum of 6 months prior to the date of filling. Revision 26 of the UFSAR incorporates applicable changes for the required updating period. The previous revision (Le., Revision 25) of the Ginna UFSAR was submitted on November 19, 2014.
Attachment i provides a brief summary of the changes incorporated into UFSAR Revision 26 and FPP Revision i 2. Attachment 2 includes the file directory structure information identifying directory path, filename, and size of the individual files on the enclosed CD-ROM.
!n accordance with Technical Specification 5.5. 13, Technical Specification Bases Control Program, Ginna's Technical Specifications Bases, Revision 76, is enclosed in Attachment 3 and incorporates changes made since November 19, 2014. Change bars indicate revisions to information which have been incorporated in the Bases pursuant to commission requirements.
In addition, pursuant to the requirements of 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision i, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses," the UFSAR update required by 10 CFR 50.71 (e) must include any Structures, Systems, or Components (SSCs) newly identified that would have been subject to an aging management review or evaluation of
U.S. Nuclear Regulatory Commission Ginna UFSAR Revision 26 and FPP Revision i2 May 5, 2016 Page 2 time-limited aging analyses in accordance with 10 CFR 54.21. The UFSAR update must describe how the licensee will manage the effects of aging in order to effectively maintain the inten,ded function(s) of newly-identified SSCs. An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting UFSAR Revision 26 for Ginna. As a result of this evaluation, there were no newly identified SSCs for which aging management reviews or time-limited aging analyses would apply.
As required by i O CFR 50.71 (e)(2}(i), I certify that to the best of my knowledge, Revision 26 of the UFSAR and Revision 12 of the FPP accurately reflects information and analyses submitted to the NAC, or prepared pursuant to NRC requirements, as described above.
If you have any questions or require further information, please contact Laura Lynch at (610) 765-5729.
Respectfully, Ja~~s~.~~~~~~~~
Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosures:
(1) CD-ROM, Ginna UFSAR, Revision 26 and Fire Protection Program, Revision 12 (2) CD-ROM, Ginna Reference Drawings Attachments: (1) Summary of Changes, Rev 26 (2) Electronic File Directory, UFSAR Rev 26 (3) Technical Specification Bases, Rev 76 cc: NRC Regional Administrator, Region 1 NRC Resident Inspector, Ginna NRC Project Manager, Ginna
