ML16357A507
Text
Exelon Generation.,,
RS-16-248 December i 5, 20 i 6 10 CFR 50.4(b)(6) 10 CFR 50.71 (e) 10 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 NRG 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 NRG Docket Nos. STN 50-454, STN 50-455 and 72-68 Updated Final Safety Analysis Report (UFSAR), Revision 16 Updated Fire Protection Report (FPR), Amendment 27 In accordance with the requirements of 10 CFR 50.71, "Maintenance of records, making of reports,"
paragraph (e)(4), Exelon Generation Company (EGG), LLC submits Revision 16 to the Updated Final Safety Analysis Report (UFSAR), Amendment 27 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 095, Byron TRM updated through Revision 107, Braidwood Technical Specifications Bases (TSB) updated through Revision 1i1 and Byron TSB updated through Revision 099). All UFSAR pages changed as a result of this update are clearly delineated with "Revision 16 - December 2016" in the page footer. All FPR pages changed as a result of this update are clearly delineated with "Amendment 27 - December 2016" in the page header.
One (1) OSM is included in this submission. The OSM labeled, "Exelon Generation - Braidwood -
Byron Stations UFSAR Revision i 6, December 2016, TRM, Tech Spec Bases, Fire Protection Rpt" contains the following four components:
001 002 003 004 BRW-BYR UFSAR REV 16.pdf, i 78 megabytes (MB), publicly available BRW-BYR TRM.pdf, Braidwood 12.2 MB, Byron 4.53 MB, publicly available BRW-BYR Tech Spec Bases.pdf, Braidwood 1.86 MB, Byron 1.80 MB, publicly available
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BRW-BYR FPR, Amend 27.pdf, i 53 MB, publicly available fl 0 f5/
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RS-16-248 December 15, 2016 U. S. Regulatory Commission Page2 Attachment A provides a brief summary of the changes incorporated into UFSAR Revision 16.
Attachment B provides a brief summary of the changes incorporated into FPR Amendment 27.
Attachment C provides a summary report pursuant to 1 O 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 16, FPR, Amendment 27, TRM, Tech Spec Bases Attachments: Attachment A-Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 Attachment B - Fire Documentation Revision Packages (FDRPs) Incorporated into Braidwood/Byron Stations Fire Protection Report - Amendment 27 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 Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 14-077 - Revised UFSAR Section 8.3.1.1.2.1 to reflect a design change on Braidwood Station, Units 1 and 2 that installed relays to detect a loss of phase on the System Auxiliary Transformers' (SAT) Division 1 and Division 2 buses.
DRP 14-090- Revised UFSAR Section 8.3.1.1.2.1 to reflect a design change on Byron Station, Unit 2 that installed relays to detect a loss of phase on the SAT Division 1 and Division 2 buses.
DRP 14-094 - Revised U FSAR Section 8.3.1.1.2.1 to reflect a design change on Byron Station, Unit 1 that installed relays to detect a loss of phase on the SAT Division 1 and Division 2 buses.
DRP 14-102 - Revised UFSAR Section 8.3.1.2 and Tables 7.3-6 and 8.3-6 to reflect a design change on Byron Station, Units 1 and 2 that added a third level of undervoltage protection to the 4kV Engineered Safety Feature (ESF) Buses via two instantaneous undervoltage relays per bus with delayed drop-out, set between the existing first and second level undervoltage protection relays.
DRP 15-004 - Revised UFSAR Table 3.5-10 to reflect a design change on Byron Station, Unit 1 that increased the quantity of helium stored on-site as a result of installation of Serveron transformer gas monitors on the Unit Auxiliary Transformers (UATs) and SATs.
DRP 15-008 - Revised UFSAR Section 9.3.4.1.2.4 to reflect isolating the Boron Thermal Regeneration System (BTRS) from the Chemical and Volume Control (CV) System on Byron Station, Unit 1.
DRP 15-018 - Revised UFSAR Section 8.3.1.2 and Tables 7.3-6 and 8.3-6 to reflect a design change on Braidwood Station, Units 1 and 2 that added a third level of undervoltage protection to the 4kV ESF Buses via two instantaneous undervoltage relays per bus with delayed drop-out, set between the existing first and second level undervoltage protection relays.
DRP 15-021 - Revised U FSAR Sections 7.3, 10.4, and 15.2 to reflect a design change on Braidwood Station, Unit 2 that installed an additional pressure transmitter in each Auxiliary Feedwater (AF) pump suction line. This design change revised the AF pump control circuit and results in a delay to AF initiation, which affects Chapter 15 analyses.
DRP 15-026 - Revised UFSAR Sections 7.3, 10.4, and 15.2 to reflect a design change on Braidwood Station, Unit 1 that installed an additional pressure transmitter in each AF pump suction line. This design change revised the AF pump control circuit and results in a delay to AF initiation, which affects Chapter 15 analyses.
DRP 15-038 - Revised UFSAR Section 3.5.4.5 to reflect a design change on Braidwood Station, Unit 1 that removed a majority of the Main Steam Safety Valve (MSSV) and Main Steam (MS) power operated relief valve (PORV) vent stack pipes from the roof of the MSSV room to mitigate the effects of a tornado driven missile to impact.
DRP 15-039 - Revised UFSAR Section 3.5.4.5 to reflect a design change on Braidwood Station, Unit 2 that removed a majority of the MSSV and MS PORV vent stack pipes from the roof of the MSSV room to mitigate the effects of a tornado driven missile to impact.
Page 1 of 10
Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 15-041 - Revised UFSAR Sections 9.1.2.3.11 and 15.7.5.2 to add information on the dry cask storage HI-TRAC/HI-STORM unrestrained stack-up configuration used at Braidwood Station in the fuel handling building to transfer the Multi-Purpose Canister (MPC) between the HI-TRAC and HI-STORM.
DRP 15-044 - Revised UFSAR Sections 1.2.6 and 10.2.2.2 and Figure 10.1-2a to reflect the re-rate of the Byron Station, Unit 1 main generator from 1361 MVA to 1400 MV A.
DRP 15-045 - Revised UFSAR Sections 1.2.6 and 10.2.2.2 and Figure 10.1-2b to reflect the re-rate of the Byron Station, Unit 2 main generator from 1361 MVA to 1396 MV A.
DRP 15-047 - Revised UFSAR Sections 1.2.6 and 10.2.2.2 and Figure 10.1-2a to reflect the re-rate of the Braidwood Station, Unit 1 main generator from 1361 MVA to 1400 MVA.
DRP 15-048 - Revised U FSAR Sections 1.2.6 and 10.2.2.2 and Figure 10.1-2b to reflect the re-rate of the Braidwood Station, Unit 2 main generator from 1361 MVA to 1396 MV A.
DRP 15-049 - Revised UFSAR Sections 7.7.1.17, 7.7.1.18, 7.7.1.20.b, 11.5.1.2.o, 1 i.5.2.1, and 12.3.4.1 to reflect a design change on Byron Station that replaced the RM-11 radiation monitoring data collection system with an upgraded system.
DRP 15-055 - Revised UFSAR Table 3.5-10 to reflect a design change on Braidwood Station, Unit 1 that increased the quantity of helium stored on-site as a result of installation of Serveron transformer gas monitors on the UATs.
DRP 15-056 - Revised UFSAR Table 3.5-10 to reflect a design change on Braidwood Station, Unit 2 that increased the quantity of helium stored on-site as a result of installation of Serveron transformer gas monitors on the UATs.
DRP 15-063 - Revised UFSAR Sections 10.4.9.1.1 and 10.4.9.2 and Table 6.2-58 to reflect a design change that added containment isolation valves to the Byron Station, Unit 1 AF System as a result of the required Diverse and Flexible Coping Strategies (FLEX) modifications.
DRP 15-067 - Revised UFSAR Section 9.1.2.3.11 to add information on the dry cask storage HI-TRAC/HI-STORM unrestrained stack-up configuration used at Byron Station in the fuel handling building to transfer the MPC between the HI-TRAC and HI-STORM.
DRP 15-069 - Revised UFSAR Sections 9.1.5.2, 9.1.5.4.2, 9.1.5.5, and 9.1.6 to revise the method used to address lifting of the reactor head to preclude loss of cooling to the vessel for Braidwood Station, Unit 1. The method is changed from a head drop analysis to use of a single failure proof equivalent polar crane per NEI 08-05, "Industry Initiative on Control of Heavy Loads."
DRP 15-070 - Revised UFSAR Table 7.2-3 to reflect a design change on Braidwood Station, Unit 1 that resulted in a change in the time delay setpoint for the reactor coolant pump (RCP) bus undervoltage (UV) signal following replacement of the RCP UV time delay relay with an NTS 812 series timing relay.
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Attachment A Draft Revision Packages {DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 15-074 - Revised UFSAR Table 3.9-16 to remove reference to Braidwood Station valve 1SX173 as an active valve and UFSAR Table 9.2-2 to remove reference to failure of valve 1SX173. Changes to UFSAR Tables 3.9-16 and 9.2-2 were required as a result of a design change on Braidwood Station, Unit 1 that converted air-operated valve, 1SX173, to a locked open manually operated valve in support of FLEX modifications.
DRP 15-075-Revised UFSAR Table 3.9-16 to remove reference to Braidwood Station valve 2SX173 as an active valve and UFSAR Table 9.2-2 to remove reference to failure of valve 2SX173. Changes to UFSAR Tables 3.9-16 and 9.2-2 were required as a result of a design change on Braidwood Station, Unit 2 that converted air-operated valve, 2SX173, to a locked open manually operated valve in support of FLEX modifications.
DRP 15-076 - Revised UFSAR Sections 10.4.9.1.1 and 10.4.9.2 and Table 6.2-58 to reflect a design change that added containment isolation valves to the Braidwood Station, Unit 1 AF System as a result of the required FLEX modifications.
DRP 15-084 - Revised UFSAR Sections 10.4.9.1.1 and 10.4.9.2 and Table 6.2-58 to reflect a design change that added containment isolation valves to the Braidwood Station, Unit 2 AF System as a result of the required FLEX modifications.
DRP 15-095 - Revised UFSAR Section 6.2.6.2 to indicate that the containment access facility (CAF) is a permanent structure at Byron Station.
DRP 15-097 - Revised U FSAR Section 15.4.6.2 discussion concerning dilution during refueling to ensure consistency between the analysis of record, Technical Specifications (TSs), plant procedures and UFSAR.
DRP 15-102 - Revised UFSAR Section 3.7.4.2.1 to reflect a design change on Byron Station that upgraded the existing seismic monitor at the river screen house to comply with the guidance in NRC Regulatory Guide (RG) 1.12, "Nuclear Power Plant Instrumentation for Earthquakes," Revision 2.
DRP 15-106 - Revised UFSAR Section 9.4.5.1.2 to reflect a design change on Byron Station that added an auxiliary building pressure control damper in the interfacing wall between the auxiliary building and the turbine building.
DRP 15-112 - Revised UFSAR Section 2.4.11.6 to clarify the reference to the single active failure in the Ultimate Heat Sink (UHS) discussion for Braidwood Station.
DRP 15-113 - Revised UFSAR Table 3.5-10 to remove references to emergency breathing air bottles located at turbine building elevation 426' since these bottles have not been used during the life of the plant and are abandoned. The volume of breathing air available is clarified for locations at turbine building elevation 401' and in the main control room. This information was removed in accordance with NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports,"
Revision 1 as information that is obsolete and no longer applicable.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 15-114 - Revised U FSAR Section 9. 1.5.4.1.5 to update compliance with ANSI B30.9-1971 to ANSI B30.9-201 Oto allow use of synthetic slings at Byron Station.
DRP 15-115 - Revised UFSAR Section 4.2.4.3 discussion regarding the Enhanced Performance Rod Cluster Control Assembly (EP-RCCA) spider body load testing requirements at the vendor facility.
DRP 15-116 - Revised U FSAR Section 11.4.2.7 to provide a description of the dry active waste storage facility at Byron Station.
DRP 15-117 - Revised UFSAR Tables 15.0-4, 15.6-2a, and 15-6-3b to reflect the current analysis input assumptions for maximum allowed steam generator tube plugging level and maximum allowed vessel average temperature for the Large Break Loss of Coolant Accident (LBLOCA} applicable to Byron and Braidwood Stations, Unit 2. The analysis was revised to offset the loss of LBLOCA peak clad temperature margin due to thermal conductivity degradation.
DRP 15-118-Deleted redundant UFSAR Sections 12.3.1.12.5, 12.3.1.12.6, 12.3.1.12.7, 12.3.1.12.8 and 12.3.1.13 due to an administrative error in incorporating a previously approved change.
DRP 15-119 - Revised UFSAR Sections 3.6.2 and 9.3.3.2 flooding area analysis discussions associated with the Essential Service Water (SX) System pump rooms and the valve pits based on a revision to the auxiliary building flood level analysis.
DRP 15-120- Revised UFSAR Sections 4.2.1.7, 4.4.1, 6.2.1.1.1, 6.2.1.3.1, and 15.6.5 to remove the discussions regarding the Braidwood Station, Unit 1 AREVA Lead Use Assembly (LUA) Program permitted during Cycles 15, 16 and i 7 and the Byron Unit 2 Axiom clad Lead Test Assembly {LTA) permitted during Cycle 16. This information is removed in accordance with NEI 98-03, Revision 1 as information that is obsolete and no longer applicable.
DRP 16-001 - Revised UFSAR Section 9.3.4.1.2.6 to clarify that nitrogen may be added to the volume control tank (VCT) at Braidwood Station up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> prior to Mode 3 to evacuate hydrogen from the VCT.
DRP 16-002 - Revised UFSAR Appendix A NRC RG 1.57, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components," compliance description for consistency with other UFSAR sections and design specifications for the containment penetration head fittings and process pipe.
DRP 16-003 Revised UFSAR Sections 9.5.4.2 and 9.5.9 to reflect a design change on Byron Station, Unit 2 that added an emergency vent path for the diesel-driven AF pump fuel oil day tanks. This design change was implemented to address tornado missile protection concerns for diesel oil systems.
DRP 16-004 - Revised UFSAR Section 9.3.4.1.2.5.i to reflect a design change on Byron Station, Unit 2 that removed BTRS relief valve 2BR7006 and replaced it with a blank flange.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-005 - Revised UFSAR Table 3.2-1 to replace incorrect reference to valves OSX162NB with reference to OSX162A-D for Byron Station.
DRP 16-008 - Revised UFSAR Sections 15.1.2.2, 15.1.5.3, 15.1.6.2, 15.3.3.4, 15.4.8.3, and 15.6.3.3 and Tables 15.0-15 and 15.6-3b to address additional changes required as a result of Measurement Uncertainty Recapture (MUR). The changes also included removing redundant information from the UFSAR in accordance with NEl 98-03, Revision 1.
DRP 16-009 - Revised UFSAR Section 9.5.3.1.a to remove excessive detail from the UFSAR regarding lighting fixture types in accordance with NEI 98-03, Revision 1.
DRP 16-010 - Revised UFSAR Sections 2.4.1.1, 2.4.11.6, 2.5.6.9, 9.2.5.1, and Figures 2.4-47 and 2.4-48 to reflect a design change on Braidwood Station that installed an underwater sheet pile wall in the cooling lake, approximately 300 feet east of the eastern slope of the Essential Service Cooling Pond (ESCP), to restore the berm height.
DRP 16-011 - Revised UFSAR Section 10.2.3. 7 to indicate that disc number four on some low pressure turbine rotors were upgraded beginning in 2008 to the Heavy Disc Keyplate (HDKP) design to address in-service cracking. In addition, Table 10.2-4 was updated to provide correct material types for the discs.
DRP 16-012-Revised UFSAR Sections 2.3.6.3.1, 15.3.3.4, 15.4.8.3, 15.6.5.3, and 15.7.4.3 and Tables 6.4-1, 6.4-1 a, 15.0-11, 15. 0-12, and 15.0-17 and the Appendix A N RC RG 1.23, "Onsite Meteorological Programs," compliance description to reflect revised Alternate Source Term calculations. The calculations corrected a RADTRAD software code error and revised offsite atmospheric dispersion factors to satisfy an NRC commitment to use finer wind speeds in determining X/Q values.
DRP 16-013 - Revised UFSAR Section 5.2.3.4.4 to describe the application of ultra-high pressure cavitation peening to the applicable reactor vessel closure head (RVCH) nozzles and J-groove welds for Byron Station, Unit 2.
DRP 16-014 - Revised UFSAR Section 5.2.3.4.4 to describe the application of ultra-high pressure cavitation peening to the applicable RVCH nozzles and J-groove welds for Braidwood Station, Unit 1.
DRP 16-016 - Revised UFSAR Section 6.2.2.2.1 to reflect a design change on Braidwood Station, Unit 1 that removed the motor space heaters from the fan/motor assemblies for the reactor containment fan coolers.
DRP 16-017 - Revised UFSAR Table 6.3-10 remarks for motor-operated gate valve 1/2Sl8811A by correcting the statement regarding valve interlocks.
DRP 16-018 - Revised UFSAR Sections 6.3.2.5 and 6.3.6 to clarify that the passive failure leak in the Emergency Core Cooling System (ECCS) is assumed to occur 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or greater after the Loss of Coolant Accident.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-019 - Revised UFSAR Section 8.3.1.1.2.3 and Table 8.3-5 to reflect a design change on Byron Station, Unit 1 that replaced the 120 VAC instrument bus inverters for bus 112 and bus 114. This included revising the power rating of the 120 VAC instrument bus inverters from 7.5 kVA to 1 O kVA for bus 112 and bus 114 and updating the description of the interlock between the inverter and constant voltage transformer (CVT) power feeds tor the new inverters.
DRP 16-020 - Revised U FSAR Section 8.3.1.1.2.3 and Table 8.3-5 to reflect a design change on Byron Station, Unit 2 that replaced the 120 VAC instrument bus inverters for busses 211, 212, 213, and 214. This included revising the power rating of the 120 VAC instrument bus inverters from 7.5 kVA to 10 kVA for busses 211, 212, 213, and 214 and the description of the interlock between the inverter and CVT power feeds for the new inverters.
DRP 16-022 - Revised U FSAR Section 7.3.1.1.15.2 to correctly reference Table 8.3-5, as opposed to Table 8.3-1, and revised Section 8.3.1.1.2.2 to replace a train specific relay description and unit specific breaker descriptions with non-train/unit descriptions.
DRP 16-023 - Revised UFSAR Section 7.7.1.2.2 and Figure 7.7-10 to reflect a design change on Braidwood Station, Unit 1 that upgraded the analog rod control system logic with the Westinghouse Ovation digital rod control system logic.
DRP 16-024 - Revised UFSAR Sections 5.4.1.2, 5.4.1.3.1, 5.4.1.3.2, and 5.4.1.3.1 Oto reflect a design change on Byron Station, Unit 1 that upgraded the RCP seal configuration employing the Westinghouse SHIELD Shutdown Seal (SOS).
DRP 16-025 - Revised U FSAR Sections 5.4.1.2, 5.4.1.3.1, 5.4.1.3.2 and 5.4.1.3.1 O to reflect a design change on Braidwood Station, Unit 2 that upgraded the RCP seal configuration employing the Westinghouse SHIELD SOS.
DRP 16-026 - Revised U FSAR Sections 5.4.1.2, 5.4.1.3.1, 5.4.1.3.2 and 5.4.1.3.1 O to reflect a design change on Byron Station, Unit 2 that upgraded the RCP seal configuration employing the Westinghouse SHIELD SDS.
DRP 16-027 - Revised UFSAR Sections 5.4.1.2, 5.4.1.3.1, 5.4.1.3.2 and 5.4.1.3.1 Oto reflect a design change on Braidwood Station, Unit 1 that upgraded the RCP seal configuration employing the Westinghouse SHIELD SDS.
DRP 16-028 - Revised U FSAR Sections 3.9.1.2 and D.8.22 to reflect the addition of computer programs utilized to analyze transients associated with the Residual Heat Removal (RHR)
System suction relief valve discharge to the recycle hold-up tank at Byron Station.
DRP 16-029 - Revised UFSAR Section 5.2.4 to include a description of the requirements for implementing an inspection program of the lncore Neutron Monitoring System thimble tubes in accordance with NRC Bulletin 88-09, "Thimble Tube Thinning in Westinghouse Reactors."
DRP 16-031 - Revised UFSAR Sections 8.2.1 and 9.5.2.1 to reflect a design change on Byron Station that removed the microwave communication system for transmission line L0627 and replaced it with a direct fiber connection into the dual fiber path JMUX fiber ring that connects Exelon/ComEd switchyards.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-032 - Revised UFSAR Sections 9.3.3.2 and 03.6 to reflect revisions to the Braidwood Station auxiliary building flood level analysis.
DRP 16-034 - Revised UFSAR Table 3.9-16 Active Valve List for Byron Station to include valves listed as active in the Byron Station lnservice Testing (IST) Program, but not previously included in UFSAR Table 3.9-16.
DRP 16-037 - Revised UFSAR Section 8.3.2.1.1 to provide clarity between the Byron and Braidwood Station descriptions of the 125 Volt battery systems.
DRP 16-038 - Revised UFSAR Sections 3.9.1.2, 3.9. 7, and 5.2.3.1 and Tables 5.2-1, 5.2-1 a, and 5.2-2, and Appendix D to reflect a design change on the Braidwood Station, Unit 2 steam generator bowl drain line to address primary water stress corrosion cracking (PWSCC) concerns in Alloy 600 weld material.
DRP 16-039 - Revised UFSAR Sections 6.3.2.5 and 6.3.6 to reflect implementation of TS Amendments to incorporate Technical Specification Task Force (TSTF) 523, "Generic Letter 2008-01, Managing Gas Accumulation."
DRP 16-041 - Revised UFSAR Sections E.75.1, E.75.4.2 and E.75.4.2.2 to remove references to microwave voice channels as an emergency communication system at Byron and Braidwood Stations.
DRP 16-042 - Revised UFSAR Table 15.6-15 to update peak clad temperatures based on the 2015 Annual 10 CFR 50.46 Report for Byron and Braidwood Stations.
DRP 16-043 - Revised UFSAR Table 6.3-1 to update the minimum available net positive suction head (NPSH) for the CV pumps and the Safety Injection (SI) pumps as a result of a revision to a design basis calculation.
DRP 16-044-Revised UFSAR Sections 6.5.3 and 9.4.8.2.1 and Tables 3.2-1and9.4-24 to reflect a design change on Braidwood Station, Unit 1 that abandoned the containment charcoal filter units subsystem.
DRP 16-045 - Revised UFSAR Sections 3.9.1.2 and 5.2.3.1 and Tables 5.2-1, 5.2-1a, and 5.2-2 to reflect a design change on the Byron Station, Unit 2 steam generator bowl drain line to address PWSCC concerns in Alloy 600 weld material.
DRP 16-047 - Added UFSAR Appendix F, "UFSAR Final Safety Analysis Report Supplement (License Renewal)," as a result of a License Condition associated with issuance of the License Renewals for Byron and Braidwood Stations to include this UFSAR supplement required by 10 CFR 54.21 (d) in the next UFSAR update.
DRP 16-048 - Deleted historical information contained in UFSAR Appendix C, Turbine Missile Study," in accordance with NEI 98-03, Revision 1 and relocated current turbine missile probability licensing basis information to UFSAR Section 10.2.3.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-049 - Deleted historical information contained in Appendix E.21, "Post-accident Sampling (11.B.3)," in accordance with NEl 98-03, Revision 1. The requirement to maintain a Post-accident Sampling System were previously eliminated as a result of TS Amendments.
DRP 16-050 - Revised UFSAR Sections 5.3.1.7, 5.3.2, and 5.3.4 and Table 5.3-2 and the Appendix A NRC RG 1.65, "Materials and Inspections for Reactor Vessel Closure Studs,"
compliance description for consistency with TS Amendments to utilize WCAP-16143-P, Revision 1, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2," dated October 16, 2014. In addition, UFSAR Tables 5.3-1 and 5.3-1 O were revised to correct an administrative error in incorporating a previously approved change.
DRP 16-051 - Revised UFSAR Sections 2.4.11.4, 6.4.4.1, 9.5.1, and 15.6.3.1 to clarify tense, revision status, and documents incorporated by reference.
DRP 16-053 - Revised UFSAR Section 2.4.11.6 to remove reference to redundant SX cooling towers at Byron Station for consistency with Section 9.2.5 and a previously incorporated change.
DRP 16-054 - Revised UFSAR Appendix A NRC RG 1.9, "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1 E Onsite Electric Power Systems at Nuclear Power Plants," compliance description for consistency with TS Amendment Nos. 187 and 194 for Braidwood and Byron Stations, respectively.
DRP 16-055 - Revised UFSAR Sections 9.5.9 and 9.5.4.2 to update the description of diesel oil storage tank vent line failure modes with respect to design basis earthquake and tornado missile loadings. The changes also reflect a design change on Byron Station, Unit 2 that provided additional venting capability in the event of normal 2B AF diesel oil day tank vent path blockage.
DRP 16-056 - Revised UFSAR Sections 4.3.3.2 and 4.3.5 to include the appropriate revisions of the LEOPARD and CINDER computer codes. Also, revised UFSAR Section 4.2.5 to include the appropriate revision of WCAP-8183, "Operational Experience with Westinghouse Cores."
DRP 16-057 - Revised UFSAR Table 11.3-10 to clarify that the flow value referenced for gland steam condenser exhaust is a "nominal" value for Byron Station, Unit 2 and Braidwood Station, Units 1 and 2.
DRP 16-060 - Revised UFSAR Table 3.2-1 to reclassify Radioactive Waste Gas (GW) System compressor skid heat exchangers at Byron Station back to Seismic Category I (Safety Quality Group C) to address quality class break concerns between the Component Cooling Water (CC)
System and the GW compressor heat exchangers.
DRP 16-062 - Revised UFSAR Sections 7.1.2.1.9 and 7.1.3 to clarify the Reactor Trip System (RTS) and Engineered Safety Feature Actuation System (ESFAS) setpoint methodology and added associated references for Byron Station, Unit 2. In addition, UFSAR Section 7.2.1.1.2.d.3 was revised as a result of a design change on Byron Station, Unit 2 that replaced the Westinghouse RCP underfrequency relays with ABB relays.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-067 - Revised UFSAR Sections 6.5.3, 9.4.8.2. 1, and 9.4.8.2. 1.2 and Table 9.4-24 to reflect a design change on Byron Station, Unit 2 that removed charcoal from the containment charcoal filter units.
DRP 16-069 - Revised Byron Station UFSAR Section 2.4. 11.6.3 to correct an administrative error in incorporating a previously approved change.
DRP 16-070 - Revised UFSAR Appendix E.20 and Figures E.20-1, Sheets 5, 7, and 8 to address additional areas that require short term occupancy for performing vital operator actions.
DRP 16-071 - Revised UFSAR Sections 7. 1.2.1.9 and 7. 1.3 to clarify the ATS and ES FAS setpoint methodology and added associated references for Byron Station, Unit 1 and Braidwood Station, Units i and 2. In addition, UFSAR Section 7.2. 1. 1.2.d.3 was revised to delete reference to the specific type of RCP underfrequency relay in accordance with NEI 98-03, Revision 1.
DRP 16-072-Revised UFSAR Appendix A NRC RG 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes, and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," compliance description to address inconsistencies in the reporting frequency between RG 1.21, Revision 1 and 10 CFR 50.36a.
DRP 16-073 - Revised UFSAR Sections 4.1 and 4.2.2.2.2 and added Figures 4.2-2C and 4.2-3 to reflect a mechanical design change to the top nozzle of the 17x17 fuel assemblies.
DRP 16-074 - Revised various sub-sections in UFSAR Sections 1.2, 4.1, 4.2, 4.3, 4.4, 15.0, 15.3, 15.4 and 15.6 to reflect the approval of Optimized ZIRLO fuel cladding in accordance with TS Amendments.
DRP 16-076 - Revised various subsections in UFSAR Sections 2.3, 5.4, 6.2, 9.2, and 15.2 for consistency with Braidwood Station TS Amendment No. 189 approving an increase in the average UHS temperature from 100°F to 102°F specified in TS Surveillance Requirement (SR) 3.7.9.2.
DRP 16-079-Revised UFSAR Section 10.4.9.3.1 and Table 3.2-1 to reflect a design change that rerouted the combustion air intake for the diesel-driven AF pumps from the 401' elevation of the turbine building to the auxiliary building 364' elevation general area to address the High Energy Line Break conditions postulated in the turbine building.
DRP 16-080 - Revised UFSAR Section 7.3.2.2.7 to reflect the as-built configuration associated with the Main Steam Isolation Valve system level switches which do not comply with IEEE Standard 279-1971. The current configuration was approved by the NRC as an alternative that would provide an acceptable level of quality and safety.
DRP 16-081 - Revised UFSAR Section 4.4.2.11.6 and Tables 4.1-i and 4.4-i to update the fuel centerline power-to-melt limit from 22.3 to 22.5 kW/ft for consistency with MUR.
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Attachment A Draft Revision Packages (DRPs) Incorporated into Braidwood/Byron Stations Updated Final Safety Analysis Report - Revision 16 DRP 16-082 - Revised the UFSAR Section 8.3.1.1.2.3 description of the 120-Vdc inverter by removing reference to providing a "ripple-free" supply of power for each ESF division's 120Vac instrumentation.
DRP 16-084 - Revised UFSAR Table 5.1-1 to reflect a design change on Braidwood Station, Unit 1 that disconnected pressurizer heater No. 37 on pressurizer heater backup group "A."
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Attachment B Fire Documentation Revision Packages (FDRPs)
Incorporated into Braidwood I Byron Stations Fire Protection Report - Amendment 27 The following Fire Documentation Revision Packages (FDRP) are being incorporated into the 2?1h Amendment of the Braidwood I Byron Fire Protection Report.
FDRP 20-017 - EC 79688 updated figures 2.3-8 Sht. 2 and 4, to reflect correct naming of "West Turbine Building Office" and "Northwest Turbine Building Office" and updated description of location of radio repeaters in Section 3.5.g to reflect correct location name of "West Turbine Building Office". Table A5.4-1 was updated for the sprinkler system in the Operator Ready Room (BYR).
FDRP 24-064 - EC 372122 revised section 2.3.9.4 and table 2.2-3 to account for additional combustible loading added to FZ 9.2-2 (BYR).
FDRP 25-065 -
EC 371033 revised page 2.3-167 to state that there is an approximate five foot long section of fire proofing missing on column Q-7, just below the 451' floor grating in Fire Zone 18.1-1 (Diesel Generator 1 B and Switchgear Room Air Shaft) (BYR).
FDRP 26-008 - EC 378236 Rev. 1 revised pages 2.3-7 and 2.2-19a due to the addition of combustible materials in Fire Zone 1.3-1 (Unit 1 Containment upper area). The Fire Protection Report will list these permanent combustibles under the combustible materials section for Fire Zone 1.3-1 (BYR).
FDRP 26-027 - EC 392478 added two chemical feed tanks outside the Lake Screen House and replaced the chemical feed house with two chemical feed buildings. Piping material for the sodium hypochlorite lines to the SX valve pits were changed from PFA to PVDF and two designated CPVC lines for yellow metal corrosion inhibitor were added and impacted the combustibles in the fire zone (BWD).
FDRP 26-031 - EC 392819 Rev. 1 revised FPR Table 2.4-4 to add new SSD Cables associated with 2AF01 PA, 2AF01 PB, 2AF006A, and 2AF006B (BWD).
FDRP 26-036 - EC 390048 Rev. 3 replaced the coating on the FHB El. 401 '. This coating is considered a combustible material and was added to the text of FPR section 2.3.12.1 under combustible materials and to Table 2.2-3 (BWD).
FDRP 26-048 - EC 389969 Rev. 1 replaced the coating on the FHB El. 401 '.This coating is considered a combustible material and was added to the text of FPR section 2.3.12.1 under combustible materials and to Table 2.2-3 (BYR).
FDRP 26-049 - EC 394153 changed 1/2SX173 from air operated valves to manually operated valves which will be locked open. 1/2SX173 were removed from the list of safe shutdown valves as they require no automatic or manual actions to perform their safety function (BWD).
FDRP 26-057 - EC 392818 revised FPR Table 2.4-4 to add new SSD Cables associated with 1AF01PA,1AF01PB,1AF006A, and 1AF006B (BWD).
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Attachment B Fire Documentation Revision Packages (FDRPs)
Incorporated into Braidwood I Byron Stations Fire Protection Report - Amendment 27 FDRP 26-062 - EC 396192 permanently routed two rubber hoses (EPDM) and one power cable (EPDM) to the boric acid mixing skid. The FPR and ATD-0026 were revised to incorporate the additional combustible material in FZ 11.5-0 (BWD).
FDRP 26-063 - EC 390750 Rev. 1 (EC 378236 Rev. 3 also)revised page 2.2-19b due to the addition of combustible material in Fire Zone 1.3-2 (Unit 2 Containment upper area) (BYR).
FDRP 26-065 - EC 397640 added WIFI Cables (combustible materials) to FZs: 8.2-2, 8.3-2, 8.5-2, 9.1-1, 9.1-2, 9.2-1, 9.2-2, 11.2-0, 11.3-0, 11.3-1, 11.3-2, 11.4-0, 11.5-0, 11.6-0, 11.7-0, and 12.1-0. The FPR was revised to account for the additional combustibles added to the zones (BWD).
FDRP 26-069 - EC 397246 replaced the installed MUDs system with mobile equipment housed in two trailers supplied by GE Water & Power. New cables and hoses were added to Fire Zone 18.22-0. This is documented in section 2.3.18.41 and table 2.2-3 (BYR).
FDRP 27-001 - EC 396879 Rev. 1 installed FME Barrier, consisting of acrylic plastic and polyester fabric, around the spent fuel pool (BWD).
FDRP 27-002 - EC 397987 extended the length and height of existing firewalls that separate the 1 E and 1W Main Power Transformers (MPTs) from each other and from the adjacent Unit Auxiliary Transformers (UATs) 141-1/2 and System Auxiliary Transformer (SAT) 142-1. Firewall extension panels were added to the existing firewalls. The existing firewalls have a 3-hour rating; the new firewall extension panels have a 2-hour rating, which meets the requirements of NFPA 850-2010 (BYR).
FDRP 27-005 - ECs 399061, 399978, and 398426 provided the option to replace existing incandescent and fluorescent lamps in the plant (BYR and BRW) with LED lamps. The replacement LED tube lights are made of plastic which contributes to the combustible loading in the respective fire zones. Addition of plastics required updates to FPR Table 2.2-3 and updates to Section 2.3 to include polypropylene to combustible materials (B/B).
FDRP 27-007 - EC 383849 extended the length and height of existing firewalls that separate the 1 E and 1W Main Power Transformers (MPTs) from each other and from the adjacent Unit Auxiliary Transformers (UATs) 141-1/2 and System Auxiliary Transformer (SAT) 142-1. Firewall extension panels were added to the existing firewalls. The existing firewalls have a 3-hour rating; the new firewall extension panels have a 2-hour rating, which meets the requirements of NFPA 850-2010 (BWD).
FDRP 27-009 - The Fire Protection Report was revised to correct a minor editorial issue that was identified in IR 2427449. In Section 2.1.4.1.a.12.c of the FPR, a portion of the last sentence was inadvertently replaced by section 2.1.4.1.a.13 when the page was revised in Amendment
- 24. This change corrected this issue (B/B).
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Attachment B Fire Documentation Revision Packages (FDRPs)
Incorporated into Braidwood I Byron Stations Fire Protection Report - Amendment 27 FDRP 27-012 - EC 392627 revised NFPA 80 Deviations to add new deviation for astragal on HELB doors into ESF Swgr rooms. New astragals on these doors, as a result of the HELB mod, allow a 3 inch gap at the bottom of the door (BYR).
FDRP 27-013 - EC 394610 added new combustibles (PVC) to Fire Zones 18.11-i and 18.11-2 (BYR).
FDRP 27-014-EC 362147 & 362149 revised SSD and FPR for instrument inverter replacements (BYR).
FDRP 27-015 - EC 389969 Rev. 2 installed a new swing arm fall protection support system to the Fuel Handling Building (FHB) column at line BB-17 to be used in maintenance activities required to support the HI-TRAC/HI-STORM unrestrained stack-up. The swing arm contains small amounts of combustible material. the combustible materials associated with the swing arm, nylon and polycarbonate (plastic), are added to FPR Table 2.2-3 and to the combustible material discussion in Section 2.3.12.1, for Fire Zone 12.1-0 (BYR).
FDRP 27-016-EC 401370 added WIFI power cables and fiber optic cables (combustible material) to Fire Zones: 8.2-1, 8.2-2, 8.3-1, 8.3-2, 8.5-1, 8.5-2, and 8.6-0 (only power cables for zone 8.6-0). The identified pages are being revised to add the combustibles to the 11Combustible Materials" description for the zones identified (BWD).
FDRP 27-017 - EC 402329 added new combustibles (hydrogen bottles) to fire zone 11.6B-O (BYR}.
FDRP 27-018-Drawing titles were changed from Braidwood Station to Byron/Braidwood Station (BYR).
FDRP 27-019-EC 390048 Rev. 6 implemented a new hydraulic jacking and PLC control system as a part of the Dry Cask Storage Campaign. This change added combustibles to Fire Zone 12.1-0 (BWD).
FDRP 27-020 - EC 362150, 362151, 362152, and 362153 replaced 120V Instrument Bus Inverters (21P05E, 06E, 07E, 08E) for Unit 2 (BYR}.
FDRP 27-021 - EC 362146 & 362148 replaced 120V Instrument Bus Inverters (1 IP05E, 07E) for Unit 1 (BYR).
FDRP 27-022-EC 396338 & 396339 added new combustibles (hydraulic fluid) to fire zones 11.3-1 & 11.3-2 (BYR}.
FDRP 27-023 - EC 401809 replaced Unit 2 Reactor Coolant Pump (RCP) #1 seal inserts with the Westinghouse RCP Passive Thermal Shutdown Seal (SOS) (BWD).
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Attachment B Fire Documentation Revision Packages (FDRPs)
Incorporated into Braidwood I Byron Stations Fire Protection Report - Amendment 27 FDRP 27-024 - EC 401137 replaced Unit 1 RCP #1 seal inserts with the Westinghouse RCP Passive Thermal SOS. The FPR added discussions with respect to tripping the RCPs to allow for a successful actuation of the SOS and included a note that the SOS is not credited in the Byron Safe Shutdown Analysis (SSA) (BYR).
FDRP 27-028 - EC 40181 O replaced Unit 1 RCP #1 seal inserts with the Westinghouse RCP Passive Thermal SOS. The FPR added discussions with respect to tripping the RCPs to allow for a successful actuation of the SOS and included a note that the SOS is not credited in the Braidwood Safe Shutdown Analysis (SSA) (BWO).
FDRP 27-029 - EC 403164 & 403165 added new fuse blocks with copper slugs (dummy fuses) to electrical penetration areas 11.5A-1, 11.5A-2, 11.6-1, and 11.6-2 (BWO).
FDRP 27-030 - EC 403306 added new combustibles in FZ 11.6-1 and 11.6-2 (BYR).
FDRP 27-031 - EC 401148 abandoned the Unit 1 Containment Charcoal Filter Unit Ventilation System. This EC isolated the manual deluge suppression system for the Containment Charcoal Filter Units and removes all filters within the HVAC plenum (BWO).
FDRP 27-032 - EC 385324 added new combustibles (lead shielding) to FZ 11.2-0 (BYR).
FDRP 27-033 - EC 402934 added new combustibles (fall protection system) to FZ 12.1-0 (BWO).
FDRP 27-034-EC 389969 Rev. 4 added new combustibles to FZ 12.1-0 (BYR).
FDRP 27-035 - EC 403334 & 403335 added new fuse blocks with copper slugs (dummy fuses) to electrical penetration areas 11.5A-1/2, 11.6-1/2 (BYR).
FDRP 27-036 - EC 396050 updated the FPR to reflect the change in oil volume for Byron 1 E and 1W MPTs (i.e., replacing 12,360 gallons of insulating oil with 20,790 gallons) (BYR).
FDRP 27-037 - EC 401138 replaced Unit 2 RCP #1 seal inserts with the Westinghouse RCP Passive Thermal SOS. The FPR added discussions with respect to tripping the RCPs to allow for a successful actuation of the SOS and included a note that the SOS is not credited in the Byron Safe Shutdown Analysis (SSA) (BYR).
FDRP 27-038 - EC 404746 revised section 2.1.4.1 to describe the acceptable configuration of unprotected auxiliary steel attached to protected structural steel (B/B).
FDRP 27-039 - EC 403991 revised page 3.5-22 to clarify that there are four repeaters (BWO).
FDRP 27-040 - EC 401150 abandoned the Unit 2 Containment Charcoal Filter Unit Ventilation System. This EC isolated the manual deluge suppression system for the Containment Charcoal Filter Units and removes all filters within the HVAC plenum (BWO).
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Attachment B Fire Documentation Revision Packages (FDRPs)
Incorporated into Braidwood I Byron Stations Fire Protection Report - Amendment 27 FDRP 27-041 -
EC 405541 removed the charcoal from the Unit 2 Containment Charcoal Filter Units and isolated the FP deluge for that system (BYR).
FDRP 27-043 - Resolved discrepancies between the FPR and actual plant conditions (BWD).
FDRP 27-046 - EC 389969 Rev. 8 superseded FDRPs26-048, 27-015, and 27-034. All additional combustible materials added to FZ 12.1-0 will be accounted for in section 2.3.12.1 and table 2.2-3 (BYR).
FDRP 27-048 - IR 02609835 recommended the following change to 003a BB FPR Chapter 3 Braidwood Guidelines BTP CMEB 9.5-1: On Page 3.1-7, change or remove reference to Nuclear Oversight Manager. This update was also included in 003c BB FPR Chapter 3 Byron Guidelines BTP CMEB 9.5-1: page 3.1-8 (B/B).
FDRP 27-049 - EC 406220 relocated the combustion air intake of the 1 B diesel-driven auxiliary Feedwater (AF) pump engine to FZ 11.3-0 (BYR).
FDRP 27-050 - EC 406221 relocated the combustion air intake of the 2B diesel-driven auxiliary Feedwater (AF) pump engine to FZ 11.3-0 (BYR).
FDRP 27-052 - FPR Table 2.4-4, "Safe Shutdown Equipment and Cables Listed by Fire Zone,"
routed cable 2RY397 through Fire Zones 2.1-0, 3.2C-2, 3.38-2, and 11.6-2. This cable was routed through FZ 3.28-2, not FZ 3.3B-2. Table 2.4-4 was updated to reflect this (BYR).
FDRP 27-053 - The stairwell in Fire Zone 11.6-1 (Div 12 Cable Penetration Area), which connects to the Div 11 cable penetration area, consists of a 2-hour fire barrier, not 3-hour.
Section 2.3.11.50 in the FPR was updated to reflect this change (B/B).
FDRP 27-054 - EC 400045 updated the FPR to account for the double fire door ODSD319 (0319) being replaced with a fire door/damper assembly. ODSD319 (0319) has been changed from a double door to a single door. FPR figure 2.3-12, Sheets 1 and 2 were updated to reflect the change (B/B).
FDRP 27-059-The FPR was updated with the latest revision of M-58 Sht. 6 and changes M-603 Sht. 15 from Braidwood to Byron (BYR).
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Attachment C 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 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 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. A review was performed at both Byron and Braidwood Stations to determine whether there were any newly identified SSCs that would have been subject to an aging management review or evaluation as a TLAA. This review, which covered the period between the final Byron and Braidwood 10 CFR 54.21 (b) annual amendment submittal and this UFSAR submittal, involved reviewing pertinent documentation and interviewing designated personnel. As a result of this review, there were no newly identified SSCs that would have been subject to an aging management review or evaluation as a TLAA.
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Attachment D OSM Directory Structure All files listed below are publicly available Directory Path File Name Size
\\001 BRW-BYR UFSAR REV. 16 000 UFSAR Cover and Page lndex.pdf 455 KB
\\001 BRW-BYR UFSAR REV. 16 001 CH 1 Intro General Plant Description.pdf 231 KB
\\001 BRW-BYR UFSAR REV. 16 002 CH 2 Site Characteristics - Braidwood.pdf 1814 KB
\\001 BRW-BYR UFSAR REV. 16 003 CH 2 Figures - Braidwood - Part 1 of 2.pdf 20502 KB
\\001 BRW-BYR UFSAR REV. 16 004 CH 2 Figures - Braidwood - Part 2 of 2.pdf 31507 KB
\\001 BRW-BYR UFSAR REV. 16 005 CH 2 Site Characteristics - Byron.pdf 1945 KB
\\001 BRW-BYR UFSAR REV. 16 006 CH 2 Figures - Byron - Part 1 of 2.pdf 3715 KB
\\001 BRW-BYR UFSAR REV. 16 007 CH 2 Fiqures - Byron - Part 2 of 2.pdf 23427 KB
\\001 BRW-BYR UFSAR REV. 16 008 CH 3 Design of SSCs.pdf 24452 KB
\\001 BRW-BYR UFSAR REV. 16 009 CH 4 Reactor.pdf 5405 KB
\\001 BRW-BYR UFSAR REV. 16 01 O CH 5 Reactor Coolant Sys.pdf 1894 KB
\\001 BRW-BYR UFSAR REV. 16 011 CH 6 Enqineered Safety Features.pdf 23543 KB
\\001 BRW-BYR UFSAR REV. 16 012 CH 7 Instrumentation and Controls.pdf 2284 KB
\\001 BRW-BYR UFSAR REV. 16 013 CH 8 Electric Power.pdf 801 KB
\\001 BRW-BYR UFSAR REV. 16 014 CH 9 Auxiliary Systems.pdf 5446 KB
\\001 BRW-BYR UFSAR REV. 16 015 CH 10 Steam and Power Conversion Sys.pdf 1082 KB
\\001 BRW-BYR UFSAR REV. 16 016 CH 11 Radioactive Waste Manaqement.pdf 1337 KB
\\001 BRW-BYR UFSAR REV. 16 017 CH 12 Radiation Protection.pdf 5354 KB
\\001 BRW-BYR UFSAR REV. 16 018 CH 13 Conduct of Operations.pdf 397 KB
\\001 BRW-BYR UFSAR REV. 16 019 CH 14 Initial Test Program.pdf 299 KB
\\001 BRW-BYR UFSAR REV. 16 020 CH 15 Accident Analyses.pdf 17704 KB
\\001 BRW-BYR UFSAR REV. 16 021 CH 16 Technical Specifications.pdf 30 KB
\\001 BRW-BYR UFSAR REV. 16 022 CH 17 Quality Assurance.pdf 20 KB
\\001 BRW-BYR UFSAR REV. 16 023 APP A Application of NRC Reg Guides.pdf 768 KB
\\001 BRW-BYR UFSAR REV. 16 024 APP B Construct Matl Standard and QA.pdf 185 KB
\\001 BRW-BYR UFSAR REV. 16 025 APP C Deleted.pdf 23 KB
\\001 BRW-BYR UFSAR REV. 16 026 APP D Computer Proqrams.pdf 2222 KB
\\001 BRW-BYR UFSAR REV. 16 027 APP E Reqmnts from TMI 2 Accident.pdf 5648 KB
\\001 BRW-BYR UFSAR REV. 16 028 APP F License Renewal.pdf 428 KB
\\002 BRW-BYR TRM 001 Braidwood TRM.pdf 12526 KB
\\002 BRW-BYR TRM 002 Byron TRM.pdf 4643 KB
\\003 BRW-BYR TECH SPEC BASES 001 Braidwood Tech Spec Bases.pdf 1910 KB
\\003 BRW-BYR TECH SPEC BASES 002 Byron Tech Spec Bases.pdf 1847 KB
\\004 BRW-BYR FPR AMEND. 27 000 FPR Cover and Paqe lndex.pdf 1579 KB
\\004 BRW-BYR FPR AMEND. 27 001 FPR CH 1.0 lntroduction.pdf 640 KB
\\004 BRW-BYR FPR AMEND. 27 002 FPR CH 2.0-2.3 Area Desiqn Haz Analysis.pdf 16462 KB
\\004 BRW-BYR FPR AMEND. 27 003 FPR CH 2.3 Fiqures Part 1 of 3.pdf 34463 KB
\\004 BRW-BYR FPR AMEND. 27 004 FPR CH 2.3 Fiqures Part 2 of 3.pdf 27084 KB
\\004 BRW-BYR FPR AMEND. 27 005 FPR CH 2.3 Fiqures Part 3 of 3.pdf 42224 KB
\\004 BRW-BYR FPR AMEND. 27 006 FPR CH 2.4 Braidwood SSA.pdf 5621 KB
\\004 BRW-BYR FPR AMEND. 27 007 FPR CH 2.4 Byron SSA.pdf 5806 KB
\\004 BRW-BYR FPR AMEND. 27 008 FPR CH 3 Braidwood Guidelines BTP CMEB.pdf 350 KB
\\004 BRW-BYR FPR AMEND. 27 009 FPR CH 3 Byron Guidelines BTP CMEB.pdf 363 KB
\\004 BRW-BYR FPR AMEND. 27 010 FPR CH 4 Fire Protection Proqram.pdf 24 KB
\\004 BRW-BYR FPR AMEND. 27 011 FPR CH 5 Aooendices.pdf 22971 KB 1of1