ML17334A214

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Rev. 27 to Updated Safety Analysis Report
ML17334A214
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/14/2017
From: Jim Barstow
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17334A213 List:
References
Download: ML17334A214 (12)
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Text

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&# 1 Exelon Generation 200 Exelon Way

..d!' Kennett Square. PA 19*343 www.exeloncorp.com 10 CF,F{ 50.71 (e) 1O CFJL54.37(b)

November 14, 2017 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-18 NRC Docket No. 50-244

Subject:

Updated Final Safety Analysis Report (UFSAR) Revision 27 Fire Protection Program (FPP) Revision 14 10 CFR 54.37(b) Aging Management Review Technical Specification Bases Changes, Revision 82 In accordance with 10 CFR 50.71 (e) and 10 CFR 50.4(b)(6), enclosed is Revision 27 of the Updated Final Safety Analysis Report (UFSAR) and Revision 14 of the Fire Protection Program (FPP) for the R.E. Ginna Nuclear Power Plant (Ginna) (Enclosure 1). The enclosed UFSAR Revision 27 and FPP Revision 14 are being provided to the NRC in electronic format on CD-ROM and are being submitted in their entirety, constituting a total replacement copy.

Additionally, Enclosure 2 contains supporting reference drawings for Revision 27 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, and the revisions must reflect all changes up to a maximum of 6 months prior to the date of filing. Revision 27 of the UFSAR incorporates applicable changes for the required updating period. The previous revision (i.e., Revision 26) of the Ginna UFSAR and Revision 12 of the FPP was submitted on May 5, 2016.

Attachment 1 provides a summary of the changes incorporated into UFSAR Revision 27 and FPP Revision 14. Attachment 2 includes file directory structure information identifying directory path, filename, and size of the individual files on the enclosed CD-ROMs.

In accordance with Technical Specification 5.5.13, Technical Specification Bases Control Program, Ginna's Technical Specifications Bases, Revision 82, is enclosed in Enclosure 3 and incorporates changes made since May 5, 2016. Change bars indicate revisions to information which have been incorporated in the Bases pursuant to commission requirements.

ft~53

.ADD~

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Submittal of Rev. 27 to the UFSAR, 10 CFR 54.37(b) Aging Management Review, and Bases Changes November 14, 2017 Page2 In addition, pursuant to the requirements of 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "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 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 intended function(s) of newly-identified SSCs. An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting UFSAR Revision 27 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.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 14th day of November 2017.

Respectfully, t~t._._ 'd T j__ J;v---- c:L.__ ~

James Barstow (J -

Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: (1) Summary of Changes, Revision 27 (2) Electronic File Directory, UFSAR Revision 27

Enclosures:

(1) CD-ROM, Ginna UFSAR, Revision 27 and Fire Protection Program, Revision 14 (2) CD-ROM, Ginna Reference Drawings (3) CD-ROM, Technical Specification Bases, Revision 82 cc: NRC Regional Administrator, Region I NRC Senior Resident Inspector, Ginna NRC Project Manager - NRA A. L. Peterson, NYSERDA

ATTACHMENT 1 Summary of Changes- UFSAR Revision 27 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 10 CFR 50.71 (e)(2)(ii) requires that revisions to the UFSAR include changes made under the provisions of 10 CFR 50.59. Accordingly, the list below identifies plant changes included in Revision 27 of the R. E. Ginna Nuclear Power Plant Final Safety Analysis Report (Updated).

Change No. Description This revision to Section 13.2.2.3 removes specific retraining frequency 026.01 requirements.

This change revises Sections 9.1.3.2.2 and 9.1.3.4.2 concerning the spent 026.02 fuel pool siphon breaker modification.

026.03 This change revises the Control Building Description (Section 3.8.4.1.2).

This change revises the description of the calibration and testing frequency 026.04 of agastat timing relays (Section 8.3.1.2.4.3).

This change revises reference errors in Sections 9.5, 13.1.3.7.2, 13.2.2.2, 026.05 13.4.1, 13.4.2, 13.4.3.1, 13.4.3.2, and 17.2.

026.06 This change corrects a typo in the R-48 upper range value in Table 7.5-1.

This change updates the Ginna FSAR for a new RW AP analysis (Sections 026.07 15.4.2, Table 15.0-2, Figures 15.4-20 and 15.4-21 ).

These changes are associated with a modification adding Safety Injection 026.08 test line isolation valves and a relief valve (Sections 6.2.4.4.2.2, 6.3.2.2.7.1, and Figure 6.2-15).

Update Table 8.3-4, "Major Battery Loads," for the newly calculated 026.09 Inverter/Auxiliary load values and revise Reference 27 of Chapter 8.

This change deleted obsolete system descriptions in Sections 2.2.2.6.1, 026.10 9.1.2.2.1, 9.2.3, and 10.7.7.1.2 and points instead to the current GE Betz water treatment system.

This change revises the discussion regarding the operation of vacuum 026.11 priming system (Section 10.7.6.3 This change makes minor editorial corrections to Section 4.2.3.2 to allow 026.12 the use of older, standard RCCA designs in 422V+ fuel.

This change adds a description of the fire water piping seismic classification 026.13 to Section 9.5.1.2.3.3.

This change corrects the description of the Closed Cooling Water surge 026.14 tank level indication systems.

These changes are associated with improvements at the intake structure to 026.15 mitigate frazil ice.

Page 1

ATTACHMENT 1 Summary of Changes- UFSAR Revision 27 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 Change No. Description These changes are associated with modification of the high pressure and 026.16 low pressure turbine valve testing frequency.

These changes to 15.0.9.2 incorporate a revised operator response time 026.17 procedure which summarizes operator action times assumed in Chapter 15.

This change to 1.8.2.32 changes the references regarding the testing of the 026.18 charcoal filter trays to the Ventilation Filter Test Program (ITS 5.5.10).

This change updates a reference in Chapter 8 regarding Design Analysis 026.19 DA-EE-97-069, Sizing of Vital Batteries A and B, to Revision 8, dated July 10, 2017.

These changes to Section 9.3.4.4.9.4 are associated with the license 026.20 amendment change (TSTF-490) to delete E-Bar and add dose equivalent xenon.

This change revises Section 6.3.5.2 and Section Note (a) of Table 15.6-17 026.21 concerning the acceptable limits of performance applied to the Residual Heat Removal pumps.

026.22 This change is associated with the spent fuel pool criticality update.

026.23 This change corrects dose figures based on past EPU changes.

This change updates the UFSAR to include a new locked rotor rods-in-DNB 026.24 analysis.

This change added Safety Injection test line relief valve 893 and associated 026.25 isolation valves.

FPPRCN- This change reflects revisions resulting from the replacement of the diesel 2016-0006 fire pump control panel per ECP-16-000342.

This change is an editorial correction only. It corrected the location of the FPPRCN- portable fire extinguishers for fire zone SH-1 (Screen House building 2016-0007 basement). The wrong location, Operating Floor, was incorrectly copied from a previous section.

FPPRCN- This change adds a description of the cable tunnel deluge system design 2016-0008 and adds an enhanced description of the use of code editions when modifications to existing systems/components are performed.

This change reflects the output of A 11014-C-001 Rev. 1 which was issued FPPRCN- under ECP-16-000608. The update reflects that the S/G pressure is below 2017-0001 the target pressure (260 psig) for TDAFW operability for 18 minutes instead of the previously stated 6 minutes, prior to S/G pressure recovery.

Page2

ATTACHMENT 2 Electronic File Directory UFSAR Revision 27, FPP Revision 14, and Reference Drawings R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 (Page 1 of 4) l___________

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ENCL0SURE1 CD-ROM, UFSAR Revision 27 and FPP Revision 14 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18

ENCLOSURE 2 CD-ROM, Reference Drawings R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18

ENCL0SURE3 CD-ROM, Technical Specification Bases - Revision 82 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18

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