ML18355A447

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Submittal of Revision 17 to Updated Final Safety Analysis Report and Amendment 28 to Updated Fire Protection Report
ML18355A447
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 12/17/2018
From: Imburgia D
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML18355A456 List:
References
RS-18-144
Download: ML18355A447 (14)
v • d • e


Text

"I Exelon Generation RS-18-144 December 17, 2018 1 O CFR 50.4(b)(6) 1 O CFR 50.71 (e) 1 O CFR 54.37(b)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20055

Subject:

Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456, STN 50-457 and 72-73 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454, STN 50-455 and 72-68 Updated Final Safety Analysis Report (UFSAR), Revision 17 Updated Fire Protection Report (FPR), Amendment 28 In accordance with the requirements of 1 O CFR 50.71, "Maintenance of records, making of reports,"

paragraph (e)(4), Exelon Generation Company (EGC), LLC submits Revision 17 to the Updated Final Safety Analysis Report (UFSAR), Amendment 28 to the Fire Protection Report (FPR) for Braidwood and Byron Stations, and summary of evaluations conducted pursuant to 1 O CFR 54.37(b), "Additional records and recordkeeping requirements".

The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (Braidwood Technical Requirements Manual (TRM) updated through Revision 100, Byron TRM updated through Revision 125, Braidwood Technical Specifications Bases (TSB) updated through Revision 120 and Byron TSB updated through Revision 111). All UFSAR pages changed as a result of this update are clearly delineated with "Revision 17 - December 2018" in the page footer. All FPR pages changed as a result of this update are clearly delineated with "Amendment 28 - December 2018" in the page header.

One (1) OSM is included in this submission. The OSM labeled, "Exelon Generation - Braidwood -

Byron Stations UFSAR Revision 17, December 2018, contains the following four components:

001 BRW-BYR UFSAR Revision 17.pdf, 179 megabytes (MB) 002 BRW-BYR TRM.pdf, Braidwood 14.6 MB, Byron 4.07 MB 003 BRW-BYR Tech Spec Bases.pdf, Braidwood 2.98 MB, Byron 2.29 MB 004 BRW-BYR FPR, Amendment 28.pdf, 174 MB Az>o/p

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RS-18-144 December 17, 2018 U. S. Regulatory Commission Page2 Attachment A provides a brief summary of the changes incorporated into UFSAR Revision 17..

Attachment B provides a brief summary of the changes incorporated into FPR Amendment 28.

Attachment C provides a summary report pursuant to 10 CFR 54.37(b).

Attachment D contains the directory path, filename, and size of each individual file.

As required by 10 CFR 50.71 (e)(2)(i), I certify that to the best of my knowledge, the information contained in the Enclosures and Attachments to this letter accurately reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provision of 10 CFR 50.59.

There are no commitments made in this document. Should you have any questions concerning this letter, please contact:

Amy Hambly Exelon Nuclear - Licensing Programs 4300 Winfield Road Warrenville, IL 60555 Phone: (630) 657-2808 E-Mail: amy.hambly@exeloncorp.com Respectfully, Dominic M. Imburgia Manager - Licensing Programs

Enclosure:

OSM - Braidwood/Byron Stations UFSAR, Revision 17, FPR, Amendment 28, TRM, Tech Spec Bases Attachments: Attachment A - Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 17 Attachment B - Fire Documentation Revision Packages (FDRPs) Incorporated into Braidwood/Byron Stations Fire Protection Report - Amendment 28 Attachment C - 10 CFR 54.37(b) Aging Management Review Summary Attachment D - OSM Directory Structure cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector-Braidwood Station NRC Senior Resident Inspector-Byron Station

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report -. Revision 17 DRP 16-015 - Revised UFSAR Section 5.2.3.4.4 to describe the application of Ultra High Pressure (UHP) Cavitation Peening to the applicable Reactor Vessel Closure Head nozzles and J-groove welds for Byron Station, Unit 1 and Braidwood Station, Unit 2.

DRP 16-:021 - Revised UFSAR Section 8.3.1.1.2.3 and Table 8.3-5 to reflect replacement of the

  • 120 VAC Instrument Bus Inverters for Electrical Bus 111 and Bus 113 on Byron Station, Unit 1.

DRP 16-030 - Revised various UFSAR Sections in Chapters 1, 2, 3, 6, 7 and 9 to reflect the '

Tornado Missile (TORMIS) Analysis implemented at Byron Station per NRC approved Byron License Amendment No. 199, issued on August 10, 2017.

DRP 16-033 - Revised UFSAR Section 6.5.1.1.2.d to clarify the Auxiliary Building exhaust system charcoal testing requirements for consistency with other ventilation system descriptions in the UFSAR.

DRP 16-035 - Revised UFSAR Sections 7.7.1.2.1 and 7.7.1.2.2 as a result of a design change that upgraded the analog rod control logic with the Westinghouse Ovation djgital rod control logic on Braidwood Station, Unit 2 DRP 16-036 - Revised UFSAR Sections 8.2.1, 8.2.2 and Figures 8.2-f, 8.2-2 and 8.2-3 to reflect the addition of the 345 kV Grand Prairie Gateway line L0626 from the Byron switchyard.

DRP 16-046 - Revised UFSAR Section 9.5.2.1 to reflect an upgrade of the dial telephone system from Private Bank Exchange (PBX) equipment to a Voice Over Internet (VOi) provider system at Braidwood Station.

DRP 16-058 - Revised UFSAR Sections 9.4.8.2.1 and 6.5.3, Tables 3.2-1, 3.10-1, and 9.4-24 and the Appendix A Regulatory Guide 1.140, "Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants," regulatory compliance description to reflect the abandonment of the Containment Charcoal Filter Units subsystem at Braidwood Station, Unit 2.

DRP 16-059 - Revised UFSAR Table 11.3-1 Oto clarify that the flow value referenced for Gland Steam Condenser Exhaust is a nominal value for Byron Station, Unit 1.

DRP 16-061 - Revised UFSAR Sections 3.7.4.2.1, 3.7.4.3 and 3.7.4.4 as a result of a design change that upgraded the seismic monitors located in the Auxiliary Building, the Containment

. and in the free field to satisfy the requirements of Regulatory Guide 1.'12, "Nuclear Power Plant Instrumentation for Earthquakes," Revision 2 at Byron Station.

DRP 16-063 - Revised UFSAR Table 3.9-16 to add new active valves to reflect revised class break classification of the Component Cooling (CC) System piping to the primary sample cooler on Byron Station, Unit 1.

DRP 16-064 - Revised UFSAR Section 9.5.2.1 to reflect a design change to upgrade the 900 MHz Security Radio at Braidwood Station.

Page 1 of 6

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report - Revision 17 DRP 16-068 - Revised UFSAR Sections 3.11.5, 6.5.2.2, 6.5.2.3, and 6.5.2.4.2 and Table 3.11-2 to clarify the containment spray and containment sump pH requirements for consistency with the Alternative Sourc;e Term methodology described in Section A6.5.

DRP 16-075 - Revised UFSAR Sections 7.7, 11.5, and 12.3 to reflect replacement of the General Atomics RM-11 Radiation Monitoring System at Braidwood Station with a new system designed by Scientech. The system was replaced due to aging hardware, hardware design and software design. Textual information in UFSAR section 11.'5.2.1 was processed as a non-regulatory change to remove excessiv*e detail in accordance with N!=I 98-03, Revision 1.

DRP 16-077-Revised UFSAR Table 3.2-1 to reclassify Waste Gas (GW) Compressor Skid Heat Exchangers back to Seismic Category I (Safety Quality Group C) to address Quality Class Break concerns between CC and the GW Compressor Heat Exchangers at Braidwood Station.

DRP 16-078-Revised UFSAR Sections 9.4.7.1.1.2, 9.4.7.1.2, 10.4.2, 11.5.2.2.13, 12.2.1.3, E.77 and UFSAR Tables 9.4-20 and 11.2-2 to reflect a design change that installed a valve block on the Offgas Vent Stack Isolation Valve in the open position to address a single point vulnerability at Byron-Station.

DRP 16-083 - Revised UFSAR Section 6.2.4.2.7 and Table 6.2-58 to reflect valves that are removed from the scope of Type C testing in the Byro"n Station Appendix J Program in accordance with a Design Evaluation.

DRP 16-086 - Revised U FSAR Section 7.3.1.1. 7 to reflect the as-built design that local control for the SX007 valves is provided by a local hand switch.

DRP 16-087 - Revised UFSAR Section 9.5.2.1 to reflect a design change that upgraded the 900 MHz Security Radio at Byron' Station.

DRP 17-001 - Revised UFSAR Sections 13.2.3 and 13.2.4 to remove references to the annual retraining frequency for General Employee Training.

DRP 17-002 - Revised UFSAR Table 6.2-22 and Table 6.2-50b to correct the revision year on pages 6.2-134c through 6.2-134g and pages 6.2-179c and 6.2-179d.

DRP 17-003 - Revised UFSAR Sections 7.7, 5.4, 9.3, and 10.4 and associated Tables and Figures to reflect a design change that upgraded 7300 NSSS Cabinets; Balance of Plant Cabinets and Feedwater Pump Control Cabinets with the Westinghouse Ovation digital system on Braidwood Station, Unit 1.

DRP 17-004 - Revised UFSAR Table 6.3-16 to address a design change that installed a local high point vent valve on Byron Station, Unit 1 inside containment on the flow path from the 1 B residual heat removal (RH) heat exchanger to reactor coolant system (RCS) cold leg injection.

DRP 17-005 - Revised UFSAR Section 9.3.4.1.3.1 to change the maximum time for boration to Mode 3 from 90 minutes to 120 minutes.

Page 2 of 6

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report-Revision 17

  • DRP 17-007-Revised UFSAR Section 6.2.1.7 and Appendix E.30 description of containment water level monitoring instrumentation as a result of a design change on Braidwood Station, Unit 2.

DRP 17-008 - Revised UFSAR Sections 3.7.4.2.1, 3.7.4.3 and 3.7.4.4 to reflect a design change at Braidwood Station that upgraded the seismic monitors located in the Auxiliary Building, the Containment and. in the free field to satisfy the requirements of Regulatory Guide 1.12, "Nuclear Power Plant Instrumentation for Earthquakes," Revision 2.

DRP 17-009 - Revised UFSAR Section 6.2.4.2.7 and Table 6.2-58 to reflect valves that are removed from the scope of Type C testing in the Braidwood Station Appendix J Program in accordance with a Design Evaluation.

DRP 17-010 - Revised UFSAR Section 10.4.7.3 to reflect a design change cin Braidwood Station, Unit 2 that modified the Feedwater (FW) Water Hammer Prevention System (WHPS) logic by installing a switch that allows enabling and disabling the FW WHPS isolation signals.

DRP 17-011 - Revised UFSAR Table 3.5-10 to reflect a maximum volume of stored nitrogen gas to the Unit Auxiliary Transformers on Byron Station, Unit 1 following replacement of Main Power Transformers that no longer utilize nitrogen gas.

DRP 17-012 - Revised UFSAR Section 9.1.4.2;2 to indicate that portions of the Braidwood Station Refueling Machine In-Mast Sipping Rings are removed unless needed to support failed fuel detection DRP 17-013 - This DRP addressed editorial corrections such as typographical errors, ineonsistencies within the UFSAR and errors in incorporating previously approved changes.

I DRP 17-014-Revised UFSAR Table 3.9-16 to include valves OSX161A and OSX161B to properly reflect that these valves are Active Valves for_Byron Station.

DRP 17-015 - Revised UFSAR Sections 7.7.1.2.1 and 7.7.1.2.2 to reflect a design change that upgraded the analog rod control logic with the Westinghouse Ovatio"n digital rod control logic on Byron Station, Unit 1 DRP 17-017 - Revised UFSAR Section 7.7.1.14 to reflect abandonment of the Main Condenser Waterbox Priming subsystem of the Offgas System for Byron Station.

DRP 17-018 - Revised the UFSAR Appendix A Regulatory Guide (RG) 8.7, "Instructions for Recording and Reporting Occupational Radiation Dose Data," compliance description to reflect compliance with Revision 3 of the RG.

I DRP 17-019 - Revised UFSAR Figures 2.4-7 and 2.4-7A to reflect installation of a new Dry Cask Storage warehouse at Braidwood Station.

DRP 17-020 - Revised UFSAR Section 4.2.2.2.3 and added Figure 4.2-6a to reflect design change details for the Fuel Assembly Top Grid Sleeve to Tube Connection.

Page 3 of 6

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report - Revision 17 DRP 17-021 - Revised Byron UFSAR Section 2.2.3.2 and Appendix A 1.91, "Evaluation of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants," to correct *1egacy reference to Braidwood UFSAR Section 2.2.3.2 which no longer exists in the UFSAR.

DRP 17-022 - Revised UFSAR Section 9.1 to clarify that the Criticality Accident Analysis complies with 1 OCFR50.68(b).

DRP 17-023 - Revised UFSAR Section 10.4.7.3.2 to reflect a design change on Byron Station, Unit 2 that modified the Feedwater (FW) Water Hammer Prevention System (WHPS) to provide the capability to enable/disable the WHPS Steam generator low level and low pressure FW Isolation signals.

DRP 17-025 - Revised Braidwood.UFSAR Table 3.9-16, Active Valve List," for consistency with the 4th Interval lnservice Testing Program.

DRP 17-026 - Revised UFSAR Sections 9.2.7.2.2, 9.2.7.4.2 and 9.4.1.2 to indicate that the service building chilled water system can be cross-tied with the control room chilled water system as a result of a design change.

DRP 17-027 - Revised UFSAR Sections 8.1.6, 8.3.2.1.1, and the Appendix A Regulatory Guide (RG). 1.32 and 1.129 compliance description for Byron Station to reflect the revision of DC Battery test frequencies from 18 months to 18 months on a staggered frequency. This DRP was processed in accordance with Byron Surveillance Frequency Control Program evaluation BY-16-001.

DRP 17-028 - Revised UFSAR Sections 3.9.7 (new), 3.9.8 (renumbered), 6.2.4.3, 6.2.7, 6.3.2.2, 6.3.6, 6.5.2.4.2, 9.1.3.2, 9.1.6, 9.2.3, and 9.2.9 to address actions taken in response to NRG Generic Letters (GL) 89-10, 95-07, 96-05 and 96-06. These changes incorporate responses previously documented under the provisions of 1 OCFR50.54(f).

DRP 17-030 - Revised Byron UFSAR Sections 2.2.2.2, 2.2.3.1.3 and Table 2.2-4 based upon results of the Control Room Envelope Habitability Chemical Surv~y.

DRP 17-031 - Revised UFSAR Table 6.2-58 to reflect the correct containment penetrations aligned with the Unit 1 Steam Generator Slowdown valves at Byron Station.

DRP 17-032 - Revised UFSAR Section 11.2.2.2 to remove excessive detail that is not important to describe the plants' design and operation consistent with RG 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants," Revision 2. These changes were processed as non-regulatory changes to remove excessive detail in accordance with NEI 98-03, Revision 1.

DRP 17-034 - Revised various sub-sections and figures of UFSAR Sections 6.2, 6.3, 6.5 and 15.6 to reflect updated Byron Emergency Core Cooling System (ECCS) and Containment Spray (CS) System flow rates in s.upport of the design basis and accident analysis.

DRP 17-035 - Revised UFSAR Tables 6.3-11 for consistency with changes made to UFSAR Table 3.9-6 as a result of Braidwood DRP 17-025.

Page 4 of 6

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report - Revision 17 DRP 17-036 - Revised UFSAR Sections 4.5.1.1.d, 15.4.8.1.1 and Table 5.2-2 to reflect the correct material for*Control Rod Drive Latch Housings and Rod Travel Housings as referenced in the Certified Material Test Reports.

DRP 17-037-Revised UFSAR Sections 15.6.5.3, 15.7.4.3, Tables 6.4-1, 6.4-1a, 15.0-12 and Table A 1.183-3 to update the Loss of Coolant Accident (LOCA) dose analysis and Fuel Handling Accident dose analysis to correct an error identified in the RADTRAD computer code.

DRP 17-038 - Revised UFSAR Table 6.2-58 to reflect the correct containment penetrations aligned with the Unit 1 Steam Generator Slowdown valves.

DRP 17-039 - This DRP addressed editorial corrections such as typographical errors, inconsistencies within the UFSAR and errors in incorporating previously approved changes.

DRP 17-040 - Revised UFSAR Section 15.6.2,2 to accurately reflect the analysis of Chemical and Volume Control System (CVCS) Letdown Line Rupture outside containment in the context of FSAR Question 311.27.

DRP 17-044 - Revised UFSAR Table 6.4-1a to clarify-the control room air intake flow value assumed,in the alternate source 'term analyses at Byron Station.

DRP 17-046 - Revised UFSAR Sections 13.1.3.1, 13.2.1 and Appendix E.4 to reflect that facility training requirements were relocated to the Quality Assurance Topical Report instead of Technical Specification (TS) 5.3.1 in accordance with Byron TS Amendment No. 203 and Braidwood TS Amendment No. 197, issued on August 2, 2018.

DRP 17-047 - Revised UFSAR Sections 5.4.7.2.5 and 5.4.15 to provide clarifying information regarding the response to NRC Generic Letter 88-17, "Loss of Decay Heat Removal."

DRP 17-049 - Revised UFSAR Appendix F, Section A.2.1.4, "Boric Acid Corrosion," aging.

management program description to provide clarifying information regarding response to NRC Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants."

DRP 17-051 - Revised UFSAR Table E.75-1 to reflect replacement of the Technical Support Center Computer Room cooling units as a result of a design change at Byron Station..

DRP 17-052 - Revised description of the area-capacity of the Braidwood Essential Service Water Cooling Pond to disposition a discrepancy between UFSAR Section 2.4.11.6 and Design Analysis ATD-0109, Revision 4.

  • ~

DRP 17-053 - Revised UFSAR Table 6.4-1a to clarify the control room air intake flow value assumed in the alternate source term analyses at Braidwood Station.

DRP 17-055 - Revised UFSAR Section 9.2.1.2.3 for consistency with UFSAR Section 8.3.1.2 to clarify that the diesel generators were specified and designed to operate for 5 minutes without a.

supply of cooling water.

Page 5 of 6

Attachment A Draft Revision Packages (DRPs) Incorporated into Byron/Braidwood Stations Updated Final Safety Analysis Report - Revision 17 DRP 17-057 - Revised UFSAR Sections 3.8.1.7.3.2, Appendix A.35 and Appendix F to reflect the latest adopted edition of ASME Section XI at Byron and Braidwood. These changes incorporate updates previously documented under the provisions of 1 OCFR50.55a(g).

DRP 17-058 - Revised UFSAR Sectlon 12.1.1.1 and Table 6.2-18a to address editorial changes that correct errors in incorporating previously approved UFSAR changes.

DRP 17-059 - Revised UFSAR Sections 8.1.6, 8.3.2.1.1 and the Appendix A Regulatory Guide (RG) 1.32 and RG 1.129 compliance descriptions for Braidwood Station to r~flect that the DC Battery Service Test frequency is performed in accordance with the Surveillance Frequency Control Program.

DRP 17-060 - Revised UFSAR Table 9.2-9 to reflect that Station Heat component 2SH11AA is not installed at Byron Station. This change was processed as a non-regulatory change in accordance with NEI 98-03, Revision 1 to delete obsolete information regarding equipment that is not installed in the plant.

DRP 17-065 - Added new UFSAR Sections 3.2.3 and 3.2.4 and revised UFSAR Sections 3.9.6, 3.10.1, 3.11, 6.2.6, and 6.6.1 to include reference to approval of implementation of 1 O CFR 50.69, "Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants," in accordance with Byron Station TS Amendment No. 204 and Braidwood TS Amendment No. 198, issued on October 22, 2018.

Page 6 of 6

Attachment B Fire Documentation Revision Packages (FDRPs)

Incorporated into Braidwood/Byron Stations Fire Protection Report - Amendment 28 The following Fire Documentation Revision Packages (FDRP) are being incorporated into the 281h Amendment of the Braidwood / Byron Fire Protection Report.

FDRP 27-006 - EC 397983 provides a new deluge system for the 1 E and 1W main power transformers for Byron Unit 1. The new deluge system has a different configuration as

  • compared to the original; however, this does not change the function of the fire suppression system. The fire protection report is being-revised to include the updated deviations table 3-1 and drawings in appendix 5.4 Figures (BYR).

FDRP 27-010--' EC 379761 provides a new deluge system for the 1 E and 1W main power transformers for Braidwood Unit 1. The new deluge system has a different configuration as compared to the original; however, this does not change the function of the fire suppression system. The fire protection report is being revised to include the updated deviations in table 3-1 and drawings in appendix 5.4 Figures (BR\\IV).

FDRP 27-025 - EC 390696, 392473 and 397451 installs polycarbonate plastic robust operational barriers throughout Braidwood Station. Table 2.2-3 and section 2.3 are updated to reflect the addition of material (BRW).

FDRP 27-028 - EC 40181 O replaces the Braidwood Unit 1 reactor coolant pump number 1 seal inserts with the Westinghouse passive thermal shutdown seals. The fire protection report adds information with respect to tripping the RCP to allow for successful actuation of thermal shutdown seals and include a note that thermal shutdown seals are not credited in Braidwood safe shutdown analysis. Updated sections include 2.4.2.3, 2.4.2.6, 2.4.2.9, 2.4.2.11, 2.4.2.13, 2.4.2.15, 2.4.2.17, 2.4.2.19, 2.4.2.21, 2.4.2.23, 2.4.2.25, 2.4.2.27, 2.4.2.33, 2.4.2.39, 2.4.2.80, 2.4.2.81, 2.4.2.97, 2.4.2.109, 2.4.2.113, 2.4.2.115, 2.4.2.117, 2.4.2.118 and 2.4.2.120 (BRW).

FDRP 27-042 - E<:; 403894 replaces OB fire pump recirculation line piping and OFP611 with a larger valve and chrome-moly piping. The fire protection report is being revised to include the updated drawing M-52 sheet number 5 in appendix A5.4 (BYR).

FDRP 27-047 - This change updates to unit 1 and 2 main power transformers fire wall extension description as an integrity barrier vice resistance barrier. Updated sections include.

2.1-10a, 2.1-10b, and 2.3.18.15 (BRW / BYR).

(

FDRP 27-051 - EC 405377 abando'i1s the Upper Cable SpreadinQ Room hose station. The fire protection report is being r$vised to update Section 2.3.3._16 and figure 2.3-7 (BYR).

FDRP 27-056 - EC 389723 extends the frequency of halon testing in the Upper Cable Spreading Rooms, CO2 testing in the Lower Cable Spreading Rooms, Diesel Generator and Diesel Generator Day tank rooms, Diesel Driven Auxiliary Feedwater Pump Rooms and associated Day tanks Rooms, cable tunnels, detection instrumentation in the auxiliary building and fuel handling building and air duct detection instrumentation. The fire protection report is being revised to capture the deviations in table 3-1 (BYR).

FDRP 28-001 - EC 404787 revises the smoke detector type at Byron-to include photoelectric detectors. section 2.2, section 2.3, section 3 and section 5.4 of the fire protection report will be updates (BYR)

Page 1 of 3

Attachment B Fire Documentation Revision Packages (FDRPs)

Incorporated into Braidwood/Byron Stations Fire Protection Report - Amendment 28 FDRP 28-002 - EC 406908 replaces the existing 900MHz analog plant radio system installed at Byron Nuclear Power Station with a-Digital 900MHz Radio System. Section 3.1 fire protection program requirements is updated for the modification (BYR).

FDRP 28-003 - EC 37085_8 and 370860 installs leading shielding blanket covers. The fire protection report is being updated to include the additional combustible material in table 2.2 and section 2.3 (BRW).

FDRP 28-005 - EC 403823 evaluates the performance of testing fire doors and the upper cable spreading room halon systems. The fire protection report requrres updating of tale 3-1 to describe the deviation from NFPA code based upon review of previous inspections (BRW).

FDRP 28-006 - ECR 418958 evaluates the use of 3 percent fh..ioroprotein foam as a replacement for foam suppression. The fire protection report will be revised to update the use of fluoroprotein foam in sections 2.2, section 2.3 and appendix A (BRW / BYR).

FDRP 28-007 - EC 383311 installs replacement 1 E and 1W Main Power Transformers. The replacement transformers contain a larger amount of oil. The fire protection report section 2.2-3, 2.3.18.15 and 2.3.18.17 are being revised to reflect the change in oil capacity (BRW).

i=DRP 28-008 - IR 3999121 identifies a deviation the diesel driven fire pump oil change frequency. Table 3-1 will be updated with an NFPA 20 deviation. In accordance with the diesel vendor manual, determining oil change intervals can be established through oil analysis methods (BRW).

FDRP 28-009-EC 403164 and 403165. This change incorporates cable's that were not included from previous amendment update under FDRP 27-029. The fire protection repqrt table 2.4 is being updated (BRW).

FDRP 28-012 - The fire protection report is updated to reflect the change of fire zone 18. 7-0 and 18.8-0 into office spaces and the removal of deluge system references for those spaces.

This change updates table A5.4 of the fire protection report (BRW / BYR).

FDRP 28-013 - EC 400449 installs lead shielding into fire zone 11.1 B-0. The fire protection report table 2.2-3 and section 2.3.11.2 is updated to reflect the new combustible loading type for the zone (BYR).

FDRP 28-014 - EC 622269 changes the normal position of 1 (2)CC9425 from normally on to normally off. The fire protection report is being updated to reflect power loc_k-out is being implemented for control of these valves at Byron and are no longer subject to spurious operation during a fire (BYR).

FDRP 28-015 - EC 622026 replaces three fuel storage tanks with two above ground fuJI storage tanks. The fire protection report figures 2.2-2, 2.3-2 and section 2.3.18-49 will be updated to reflect the changes (BRW).

Page 2 of 3 I

Attachment B Fire Documentation Revision Packages (FDRPs)

Incorporated into Braidwood/Byron Stations Fire Protection Report - Amendment 28 FDRP 28-017 - EC 403334 and 403335 modifies the mitigating actions of the pressurizer PORVs for failing closed in the event of a design basis fire in the main control room or cable spreading room. The change installs new fuse block enclosures containing dummy fuses in line with the DC control power. The fire protection report will be updated to revise the action to pull dummy fuses from the newly installed fuse blocks in section 2.4.3.2 (BYR).

FDRP 28-018 - EC 622026 modifies the mitigating strategies for the pressurizer PORY by installing new fuse block enclosures containing dummy fuses in line with the DC control power.

This change request-incorporates cable numbers for the pressurizer PORV dummy fuse circuitry in section 2.4 (BRW).

FDRP 28-020 - Adds combqstible loading associated with ladder storage areas that contain fiberglass ladders and office furniture in fire zone 11.6-2. This change updates table 2.2 and section 2.3 for Byron (BYR).

, FDRP 28-022-IR 4140755 identified discrepancies in FPR tables refenced in th~ fire protection report. Table 2.4-7 through 2.4-11 were incorporated into table 2.4.-6. Tables 2.4-7 through 2.4-11 that are referenced will be_ updated to reflect table 2.5-6. The size of the SX cooling pond at Braidwood will be revised to reflect the sizer stated in the UFSAR (BRW/ BYR).

This FDRP updates section 1.2 general description of facility, 2.1 station layout, and section 2A for Braidwood and Byron (BRW/BYR).

FDRP 28-024 - EC 618117 adds wireless control system for the reactor cavity maintenance crane. The fire protection report section 2.3 is being revised to include the added combustible material (BRW)

FDRP 28-025 - EC 620024 rewires the 2E and 2W main power transformer cooling circuitry so that each cooling control circuitry for a cooler group is independent of one another. The fire protection report table 2.2 and section 2.3 is being updated to reflect this combustible loading (BRW)

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Attachment C Braidwood Station 10 CFR 54.37(b) Aging Management Review Summary In accordance with 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of the 10 CFR 54.37(b) for Holders of Renewed Licenses," the UFSAR update required by 1 O CFR 50.71 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 1 O CFR 54.21. This UFSAR update must describe how the effects of aging will be managed such that the intended function(s) in 1 O CFR 54.4(b) will be effectively maintained during the period of extended operation..

The 1 O CFR 54.37(b) review of changes to the plant Current Licensing Basis covered the period of September 28, 2016 to November 8, 2018. The review includec;I:

Interviews of Program Managers/SME's, Engineering Changes that were installed or completed since the last UFSAR update, Changes to component classifications,

  • UFSAR pending change descriptions and revised text, NRG Interim Staff Guidelines (ISGs) related to license renewal, and Licensing Corresp~ndence to and from the NRG.

. No "newly identified" SSCs were identified that require aging management or evaluation of TLAA's in accordance with the License Renewal Rule. Therefore, there are no associated updates required to the Braidwood UFSAR and Aging Management Programs.

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Attachment C Byron Station 10 CFR 54.37(b) Aging Management Review Summary In accordance with 1 O CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of the 10 CFR 54.37(b) for Holders of Renewed Licenses," the UFSAR update required by 1 O CFR 50.71 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 1 O CFR 54.21. This UFSAR update must describe how the effects of aging will be managed such that the intended function(s) in 1 O CFR 54.4(b) will be effectively maintained during the period of extended operation.

The 1 O CFR _54.37(b) review of changes to the plant Current Licensing Basis covered the period of September 28, 2016 to November 8, 2018. The review included:

Interviews of Program Managers/SME's, Engineering Changes that were installed or completed since the last UFSAR update, Changes to component classifications, UFSAR pending change descriptions and revised text, NRC Interim Staff Guidelines (ISGs) related to license renewal, and Licensing Correspondence to and fro~ the NRC.

No "newly identified" SSCs were identified that require aging management or evaluation of TLAA's in accordance with the License Renewal Rule. Therefore, there are no associated updates required to the Byron UFSAR and Aging Management Programs.

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Attachment D OSM Directory Structure Directory Path File Name Size

\\001 BRW-BYR UFSAR REV. 17 000 UFSAR Cover and Page lndex.pdf 350 KB

\\001.BRW-BYR UFSAR REV. 17 001 CH 1 Intro General Plant Description.pdf 231 KB

\\001 BRW-BYR UFSAR REV. 17 002 CH 2 Site Characteristics - Braidwood.pdf 54244 KB

\\001 BRW-BYR UFSAR REV. 17 003 CH 2 Site Characteristics - Byron.pdf 28951 KB

\\001 BRW-BYR UFSAR REV. 17 004 CH 3 Desiqn of SSCs.pdf 24854 KB

\\001 BRW-BYR UFSAR REV. 17 005 CH 4* Reactor.pdf 5421 KB

\\001 BRW-BYR UFSAR REV. 17 006 CH 5 Reactor Coolant Sys.pdf 2354 KB

\\001 BRW-BYR UFSAR REV. 17 007 CH 6 Enqineered Safety Features.pdf 22298 KB

\\001 BRW-BYR UFSAR REV. 17 008 CH 7 Instrumentation and Controls.pdf 2766 KB

\\001 BRW-BYR UFSAR REV. 17 009 CH 8 Electric Power.pdf 1037 KB

\\001 BRW-BYR UFSAR REV. 17 010 CH 9 Auxiliary Systems.pdf 5859 KB

\\001 BRW-BYR UFSAR REV. 17 011 CH 10 Steam and Power Conversion Sys.pdf 1089 KB

\\001 BRW-BYR UFSAR REV. 17 012 CH 11 Radioactive Waste Manaqement.pdf 939 KB

\\001 BRW-BYR UFSAR REV. 17 013 CH 12 Radiation Protection.pdf 5464 KB

\\001 BRW-BYR UFSAR REV. 17 014 CH 13 Conduct of Operations.pdf 350 KB

\\001 BRW-BYR UFSAR REV. 17 015 CH 14 Initial Test Program.pdf 316 KB

\\001 BRW-BYR UFSAR REV. 17 016 CH 15 Accident Analyses.pdf 17826 KB

\\001 BRW-BYR UFSAR REV. 17 017 CH 16 Technical Specifications.pdf 25 KB

\\001 BRW-BYR UFSAR REV. 17 018 CH 17 Quality Assurance.pdf 16 KB

\\001 BRW-BYR UFSAR REV. 17 019 APP A Application of NRG Req Guides.pdf 959 KB

\\001 BRW-BYR UFSAR REV. 17 020 APP B Construct Matl Standard and QA.pdf 171 KB

\\001 BRW-BYR UFSAR REV. 17 021 APP C Deleted.pdf 25 KB

\\001 BRW-BYR UFSAR REV. 17 022 APP D Computer Proqrams.pdf 2259 KB

\\001 BRW-BYR UFSAR REV. 17 023 APP E Reqmnts from TMI 2 Accident.pdf 5702 KB

\\001 BRW-BYR UFSAR REV. 17 024 APP F License Renewal.pdf 354 KB

\\002 BRW-BYR TRM 001 Braidwood TRM.pdf 14962 KB

\\002 BRW-BYR TRM 002 Byron TRM.pdf 4174 KB

\\003 BRW-BYR TECH SPEC BASES 001 Braidwood Tech Spec Bases.pdf 3054 KB

\\003 BRW-BYR TECH SPEC BASES 002 Byron Tech Spec Bases.pdf 2350 KB

\\004 BRW-BYR FPR AMEND. 28 000 FPR Cover and Page lndex.pdf 2205 KB

\\004 BRW-BYR FPR AMEND. 28 001 FPR CH 1.0 lntroduction.pdf 997 KB

\\004 BRW-BYR FPR AMEND. 28 002 FPR CH 2.0-2.3 Area Desiqn Haz Analysis.pdf 16924 KB

\\004 BRW-BYR FPR AMEND. 28 003 FPR CH 2.3 Fiqures Part 1 of 2.pdf 31243 KB

\\004 BRW-BYR FPR AMEND. 28 004 FPR CH 2.3 Fiqures Part 2 of 2.pdf 70578 KB

\\004 BRW-BYR FPR AMEND. 28 005 FPR CH 2.4 Braidwood SSA.pdf 5126 KB

\\004 BRW-BYR FPR AMEND. 28 006 FPR CH 2.4 Byron SSA.pdf 5615 KB

\\004 BRW-BYR FPR AMEND. 28 007 FPR CH 3 Braidwood Guidelines BTP CMEB.pdf 430 KB

\\004 BRW-BYR FPR AMEND. 28 008 FPR CH 3 Byron Guidelines BTP CMEB.pdf 339 KB

\\004 BRW-BYR FPR AMEND. 28 009 FPR CH 4 Fire Protection Proqram.pdf 23 KB

\\004 BRW-BYR FPR AMEND. 28 010 FPR CH 5 Aooendices.pdf 45041 KB 1 of 1

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