RS-14-128, LaSalle, Units 1 & 2, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 20
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V 4300 Winfield Road Warrenville, IL 60555 SEGeneration 630 657 2000 Office Withhold from Public Disclosure in accordance with 10 CFR 2.390.Upon removal of enclosed optical storage media (OSM), this letter is decontrolled.
RS-14-128 10 CFR 50.71(e)10 CFR 50.59 10 CFR 72.48 April 11, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-1 8 NRC Docket Nos. 50-373, 50-374, and 72-70
Subject:
LaSalle County Station Updated Final Safety Analysis Report (UFSAR), Revision 20 In accordance with the requirements of 10 CFR 50.71, "Maintenance of records, making of reports," paragraph (e)(4), Exelon Generation Company (EGC), LLC submits Revision 20 to the Updated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 6 to the Fire Protection Report (FPR) and summaries of evaluations conducted pursuant to 10 CFR 50.59, "Changes, tests, and experiments" and 10 CFR 72.48. "Changes, tests, and experiments." The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (e.g., Technical Requirements Manual and Technical Specifications Bases). All UFSAR pages changed as a result of this update are clearly delineated with "Rev. 20, APRIL 2014" in the page footer.Some of the information in the TRM (Appendix J, Unit 2 Cycle 15 COLR, Revision 1) is proprietary to GNF-A, and is supported by a signed affidavit from the owner of the information.
The affidavit, which is provided within the applicable document, sets forth the basis on which the information may be withheld from public disclosure by the NRC, and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding." Accordingly, it is respectfully requested that the information be withheld from public disclosure in accordance with 10 CFR 2.390. A non-proprietary version is also provided.Two OSMs are included in this submission.
The OSM labeled, "Exelon Nuclear -LaSalle County Station UFSAR Rev. 20, April 2014- Proprietary," contains the following components:
001 LAS UFSAR Rev. 20.pdf, 649 megabytes, publicly available 002 LAS TRM -Proprietary.pdf, 7.42 megabytes, proprietary 003 LAS Tech Spec Bases.pdf, 2.04 megabytes, publicly available 004 LAS FPR Rev. 6.pdf, 10.7 megabytes, publicly available Withhold from Public Disclosure in accordance with 10 CFR 2.390.Upon removal of enclosed optical storage media (OSM), this letter is decontrolled.
April 11,2014 U. S. Nuclear Regulatory Commission Page 2 The OSM labeled, "Exelon Nuclear -LaSalle County Station UFSAR Rev. 20, April 2014-Non-Proprietary," contains the following components:
001 LAS UFSAR Rev. 20.pdf, 649 megabytes, publicly available 002 LAS TRM -NP.pdf, 5.99 megabytes, publicly available 003 LAS Tech Spec Bases.pdf, 2.04 megabytes, publicly available 004 LAS FPR Rev. 6.pdf, 10.7 megabytes, publicly available Attachment A provides a brief summary of the changes incorporated into UFSAR Revision 20.Attachment B provides a brief summary of the changes incorporated into the FPR.Attachment C provides the summary report pursuant to 50.59(d)(2).
These activities were evaluated in accordance with the requirements of 10 CFR 50.59, and were implemented in calendar years 2012 and 2013. Attachment D provides the initial LaSalle County Station summary report pursuant to 72.48(d)(2).
This report indicates that no 10 CFR 72.48 evaluations were performed from the initiation of dry cask storage activities through the end of 2013. Attachment E contains the directory path, filename, and size of each individual file.As Manager-Licensing, I certify that the information in this submittal accurately presents changes made since the previous submittal necessary to reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provisions of 10 CFR 50.59 and 10 CFR 72.48.There are no commitments in this letter. Should you have any questions concerning this submittal, please contact Amy Hambly at (630) 657-2808.Reset ly Patrick R. Simpson Manager -Licensing Attachments:
Attachment A, "LaSalle UFSAR Revision 20 Change Summary Report" Attachment B, "LaSalle FPR Revision 6 Change Summary Report" Attachment C, "LaSalle 10 CFR 50.59 Evaluation Summary Report" Attachment D, "LaSalle 10 CFR 72.48 Evaluation Summary Report" Attachment E, "OSM Directory Structure" cc: Regional Administrator
-NRC Region III NRC Senior Resident Inspector
-LaSalle County Station ATTACHMENT A LaSalle UFSAR Revision 20 Change Summary Report LUCR-0152 Revision to UFSAR Table 3.2-1. Section 3.4.1.4.a.2.
and Appendix J Revised UFSAR Table 3.2-1 to add note that selected Service Water piping has been analyzed to Seismic Category I standards.
Revised Section 3.4.1.4.a.2 and Appendix J to reflect how the 48" Service Water return water standpipes discussed above were analyzed to meet the crack exclusion criteria.LUCR-0220 Revision to UFSAR Table 12.3-17 Revised UFSAR Table 12.3-17 to transition the drywell continuous air monitors particulate alarm point criteria from the UFSAR to procedural controls.LUCR-0241 Revision to UFSAR Sections 9.1.2.1.3.3 and 11.4.2.7 Revised UFSAR Sections 9.1.2.1.3.3 and 11.4.2.7 to expand the discussion of the spent fuel cask well to include an identification of the low-level waste (LLW) storage racks and compaction equipment being added to the Spent Fuel Pool.LUCR-0245 Revision to UFSAR Sections 12.5.3.2 and 13.2.1.1.3 Revised UFSAR Sections 12.5.3.2 and 13.2.1.1.3 to document change from thermoluminescent dosimeter (TLD) to dosimeter of legal record (DLR).LUCR-0248 Revision to UFSAR Section 3.8.4.4. 9.1.4.3.1.
and Appendix B Revised UFSAR Section 3.8.4.4, 9.1.4.3.1, and Appendix B, to update dry cask description regarding tornado loading.LUCR-0249 Revision to UFSAR Section 12.3.1 Revised UFSAR Section 12.3.1 to remove references to the in-plant first aid room, and to update information about the mask wash facility.LUCR-0252 Revision to UFSAR Table 6.2-21 (Unit 2)Revised UFSAR Table 6.2-21, Sheet 49 Note 57 to reflect the configuration after modification per Engineering Change (EC) 375186.LUCR-0253 Revision to Multiple UFSAR Sections to Incorporate GNF2 Fuel Design Revised multiple UFSAR sections to incorporate GNF2 Fuel Design.LUCR-0254 Revision to UFSAR Sections 7.7.14 and 11.3.2 Revised UFSAR Sections 7.7.14 and 11.3.2 to clarify description of Off-Gas post-treatment high rad bypass logic.Page 1 of 5 ATTACHMENT A LaSalle UFSAR Revision 20 Change Summary Report Revision to UFSAR Appendix G Section G.2.1.1.1 LUCR-0255 Revised UFSAR Appendix G, Section G.2.1.1.1 to document the potential of an alternate insulation material to be installed on the Reactor Recirculation System Flow Control Valve.LUCR-0258 Revision to UFSAR Appendix J. Section J.1 Revised UFSAR Appendix J, Section J.1 to correct typos and clarify wording.LUCR-0259 Revision to UFSAR Table 3.2-1 Revised UFSAR Table 3.2-1 to clarify that Low-Pressure Core Spray System (LPCS) valves beyond the outermost isolation valves and cables with a safety function have an electrical classification of 1 E.LUCR-0260 Revision to Multiple UFSAR Sections to Support Increasing Maximum Allowed UHS Temperature Revised multiple UFSAR sections to support Increasing Maximum Allowed Ultimate Heat Sink (UHS) Temperature from 104 to 107 degrees F.LUCR-0261 Revision to UFSAR Sections 9.1.2.2.3.1 and 9.1.2.2.4 Revised UFSAR Sections 9.1.2.2.3.1 and 9.1.2.2.4 to reflect that installation of Netco Snap-In inserts in all accessible locations in the Unit 2 Spent Fuel Pool was complete.LUCR-0262 Revision to Multiple UFSAR Sections to Correct Editorial and Typographical Errors Revised multiple UFSAR sections to correct editorial and typographical errors.LUCR-0263 Revision to UFSAR Section 10.4.7.2 Revised UFSAR Section 10.4.7.2 to correct description of condensate pumps from multi-stage to single stage.LUCR-0264 Revision to UFSAR Sections 6.3.2.2.5 and 6.3.6 Revised UFSAR Sections 6.3.2.2.5 and 6.3.6 to add discussion regarding the Station's response to Generic Letter (GL) 2008-01 for managing gas accumulation.
LUCR-0265 Revision to UFSAR Table 5.2-9 Revised UFSAR Table 5.2-9 to correct a discrepancy between the Safety Relief Valve (SRV) flow capacities identified in the table and the nameplate flow capacities.
The UFSAR is revised to reflect the nameplate flow capacities, which are slightly higher.Page 2 of 5 ATTACHMENT A LaSalle UFSAR Revision 20 Change Summary Report LUCR-0266 Revision to UFSAR Sections 1.2. 3.8, 11.4, Tables 11.4-1 and 12.3-6 Revised UFSAR Sections 1.2, 3.8,11.4, Tables 11.4-1 and 12.3-6 to address the new Low Level Waste Storage location using HI-SAFE casks.LUCR-0267 Revision to UFSAR Tables 3.2-2. 3.2-3. and 3.2-4. and Section 7.5.2.2.2 Revised UFSAR Tables 3.2-2, 3.2-3, and 3.2-4, and Section 7.5.2.2.2 for ASME Section III and B31.1 Code reconciliation.
LUCR-0268 Revision to UFSAR Sections 1.2.3.1.1, 10.2.2 and Figure 8.1-3 Revised UFSAR Sections 1.2.3.1.1, 10.2.2 and Figure 8.1-3 to reflect the new Unit 2 generator nameplate rating.LUCR-0269 Revision to UFSAR Section 3.1.2.2.9.b and Appendix B Revised UFSAR Section 3.1.2.2.9.b and Appendix B to state that the surveillance frequency for the EDG protective-Trip Bypass Test will be controlled under the surveillance frequency control program.LUCR-0270 Revision to UFSAR Table 8.3-2 Revised UFSAR Table 8.3-2 to add open phase detection relays as protective devices for the ESF 4160 volt buses for Unit 2.LUCR-0271 Revision to UFSAR Sections 2.5.5.2.5 and 2.5.7.1 Revised UFSAR Sections 2.5.5.2.5 and 2.5.7.1 to clarify the effects of large fish kills on the shad net.LUCR-0272 Revision to UFSAR Sections 2.4.2.3. 3.4.1.1. and 3.4.1.3 Revised UFSAR Sections 2.4.2.3, 3.4.1.1, and 3.4.1.3 to update UFSAR with new results from calculations performed due to issues noted during Fukushima flooding walkdowns.
This change also clarifies what buildings are required to resist external flood.LUCR-0273 Revision to UFSAR Sections 6.3.2.2. 7.3.1.2. Tables 6.2-21 and Fiqure 6.2-31 Revised UFSAR Sections 6.3.2.2, 7.3.1.2, Tables 6.2-21 and Figure 6.2-31 to indicate the removal of the air actuators on Emergency Core Cooling System (ECCS) check valves and the installation of new manual locking mechanisms.
LUCR-0274 Revision to UFSAR Section 7.6.2.2.6 Revised UFSAR Section 7.6.2.2.6 to delete the statement regarding the bypass of Reactor Water Clean Up (RWCU) differential flow signals during heatup and cooldown.Page 3 of 5 ATTACHMENT A LaSalle UFSAR Revision 20 Change Summary Report LUCR-0275 Revision to UFSAR Sections 11.4.1.1.
Tables 11.4-1 and 11.4-2. Sections 11.4.1.4 and 11.4.2.7 Revised UFSAR Sections 11.4.1.1, Tables 11.4-1 and 11.4-2, Sections 11.4.1.4 and 11.4.2.7 to describe use of the Interim Radwaste Storage Facility (IRSF) building to store low-level radioactive waste from other Exelon sites in accordance with License Amendment 202/189.LUCR-0276 Revision to UFSAR Section 15.2.10 Revised UFSAR Section 15.2.10 to add a discussion of the Loss of Stator Cooling Event.LUCR-0277 Revision to UFSAR Sections 4.1.2.1.2.
15.9.3.1 and 15.9.5 Revised UFSAR Section 4.1.2.1.2 to incorporate the reintroduction of GNF2 fuel in LaSalle Unit 2.Revised UFSAR Sections 15.9.3.1 and 15.9.5 to incorporate the reintroduction of GNF2 fuel in LaSalle Units 1 and 2 on the Station's blackout coping capability.
LUCR-0278 Revision to UFSAR Sections 3.9.5.1. 4.1.2.4, 5.2.3.3. 5.3.1.6. 5.3.3.1. 5.3.4 and Table 5.2-12 Revised UFSAR Sections to reflect removal of Unit 1 120 degree surveillance capsule.LUCR-0280 Revision to UFSAR Table 8.3-2 Revised UFSAR Table 8.3-2 to add SAT protective relay description, including loss of phase for Unit 1.LUCR-0282 Revision to UFSAR Sections 3.3.2.2.3 and 3.5.2.1 Revised UFSAR Sections 3.3.2.2.3 and 3.5.2.1 to clarify/enhance the discussion of the protection of safety-related systems and components from tornado missiles.LUCR-0285 Revision to UFSAR Table 6.2-21 Revised UFSAR Table 6.2-21 Note 3 to clarify description of ECCS and Residual Heat Removal (RHR) shutdown cooling return testable check valves.LUCR-0287 Revision to UFSAR Section 8.1.2.5 and Fiqures 8.1--1. 8.1-2 and 8.1-4 Revised UFSAR Section 8.1.2.5 and Figures 8.1-1. 8.1-2 and 8.1-4 to describe battery, charger and DC system for the 138 kV switchyard, and to show 138 kV connections to Kickapoo Creek substation.
Page 4 of 5 ATTACHMENT A LaSalle UFSAR Revision 20 Change Summary Report LUCR-0289 Revision to UFSAR Section 6.3 Revised UFSAR Section 6.3 to incorporate the new GEH LOCA analysis for the ATRIUM-10 fuel in LaSalle Unit 2. This analysis was performed by GEH in conjunction with the new fuel introduction for GNF2 fuel.LUCR-0290 Revision to UFSAR Section 8.3.1.1.2 Revised UFSAR Section 8.3.1.1.2 to indicate that the offsite power source to the ESF Division 1 and 2 buses 141Y(241Y) and 142Y(241Y) is considered to be inoperable if these buses are being fed from the unit onsite power source through UAT 141 (241) during unit operation.
LUCR-0293 Revision to UFSAR Sections 4.1.2.1.1 and 4.1.3.2 Revised UFSAR Sections 4.1.2.1.1 and 4.1.3.2 to add discussion of the Marathon Ultra Control Blade.LUCR-0295 Revision to UFSAR Sections 6.3. 6.B. 15.2. 15.6. 15.A. Figure 6.3. Tables 6.3 and 15.A Revised UFSAR Sections 6.3, 6.B, 15.2, 15.6, 15.A, Figure 6.3, Tables 6.3 and 15.A, to incorporate GEH LOCA Analysis for ATRIUM-10 fuel for Unit 1 and remove AREVA LOCA Analysis for ATRIUM-10 fuel. Loss of Stator Cooling (LOSC) updated to match turbine runback assumption.
Incorporate GEH review of reload specific information in Chapter 15 and remove discussion of cycle specific analysis performed by AREVA.Page 5 of 5 ATTACHMENT B LaSalle FPR Revision 6 Change Summary Report FDRP Descriptioni LF2012-001 LF2012-001 revised the Fire Protection Report Tables H.4-60, H.4-62, H.4-63, H.4-65 and H.4-69. In addition, Section H.4.2.46.2 (Page H.4-35), Section H.4.2.47.1 (Page H.4-36), Section H.4.2.48.1 (Page H.4-37), Section H.4.2.49.1 (Page H.4-39), Section H.4.2.52 (Page H.4-41). The activity incorporated the following:
- 1) The addition of cable 1 NBE1 05 for a Unit 1, Division 1 SRV Bypass Switch. The switch allows the bypass of SRVs 1 B21 -FO1 3H, K and P.2) The addition of a Unit 1 Division 1 SRV Bypass Switch.3) The addition of cable 2NBE105 for a Unit 2, Division 1 SRV Bypass Switch. The switch allows the bypass of SRVs 2B21-FO13H, K and P.4) The addition of a Unit 2 Division 1 SRV Bypass Switch.LF2012-002 LF2010-002 revised the Fire Protection Report for the following activities:
- 1) Removed cables 2RH020 & 2RH1 10 from Fire Zones 4E2-1 and 4E2-2 in Table H.4-61 and Table H.4-62. Removed cables 2RH020, 2RH078, 2RH1 10 & 2RH1 17 from Fire Zone 4E2-1 Table H-4-61.2) Removed the following cables from the Fire Protection Report that are not in the following Fire Zones: a) Fire Zone 4D3 Table H.4 Cables 1 RH419, 1 RH501, 1 RH502, 1AP123, 1AP124, 1AP128, 1AP129, 1AP135, 1AP136, 1AP170, 1AP171, 1AP443, 1DC034, 1DG082, 1DG083, 1DG124, 1NB356 and 1 R1021.b) Fire Zone 4E1-1 Table H.4 Cables 1RH419, 1AP123, 1AP124, 1AP128, 1AP129, 1AP135, 1AP136, 1AP170, 1AP171, 1AP443, 1 DC034, 1 DG082, 1 DG083 and 1 DG 124.c) Fire Zone 4F1 -Table H.4 Cables 1 RH031, 1 RH042, 1 RH050, 1RH074, 1LP021, 1LP031, 1LP060, 1 R1039, 1R1040, 1RI060, 1 R1061, 1 RI070, 1 R1072, 1 R1079, 1 R1084, 1 R1096, 1 R1097, 1 R1098 and 1 RI 198.d) Fire Zone 4F3 Table H.4 Cables 1 DC036 and 1 DC040.3) Clarified that the I-IPCS cables that pass through Fire Zones 4D3 (Section H.4.2.44), 4D4 (Section H.4.2.45), 4F1 (Section H.4.2.50), and 4F2 (Section H.4.2.51) are embedded in the wall and are thus protected.
- 4) Revised the Safe Shutdown Analysis (SSA), to credit ADS Division I in Fire Zone 3H3 (Section H.4.2.19) instead of ADS Division 2 which is part of the basic method that is credited.5) Revised the Fire Hazards Analysis Fire Zones 4D3 (Section H.3.4.10)and 4D4 (Section H.3.4.11) as well as Table H.3-2 to remove statements about fire detectors being in the 24/48 volt battery rooms.6) Revised the Fire Protection Report Section 5, Code Deviation Summary Matrix sections 90A-2 and 803-12 to remove statements about Class I filters since UL 900 will no longer be classifying filters as Class I based on EC 388391 Revision 0.Page 1 of 2 ATTACHMENT B LaSalle FPR Revision 6 Change Summary Report FDRP F Description 13-001 L1 F2013-001 revised the Fire Protection Report Table H.4-48 Sheet 2 of 3.This activity removed cables 1 NB901, 1 NB902, 1 NB905, 1 NB909 and 1 NB916 from Fire Zone 2J.LF2013-002 LF2013-002 revised Fire Protection Report Sections H.4.2.15.1, H.4.2.42.2, H.4.2.44, H.4.2.45, H.4.2.46.2 and H.4.2.48.2.
This activity revised the Fire Protection Report (FPR) to credit recorder 1 LR-CM028 in fire zones that contain indicator 1 LI-CM032.
Both of these instruments are shown on FPR Table H.4-108 and both instruments are located in the Main Control Room (MCR). Both instruments are part of the same loop and both instruments provide the same information.
LF2013-003 LF2013-003 revised the Fire Protection Report Tables H.4-2, H.4-3, H.4-4, H.4-6, and H.4-106 to correct typographical errors. This activity also revised the Fire Protection Report Table H.3-1 to remove the Main Steam Isolation Valve Leakage Control System (MSIV-LCS) that has been abandoned in-place on Unit 1 and deleted on Unit 2 as documented in UFSAR Chapter 6.7.
Reference:
FPR Table H.3-1 page 8 and UFSAR Chapter 3.11.1.2, page 3.11-12.LF2013-004 LF2013-004 revised Fire Protection Report Section 5, page 5.2-63 to allow an NFPA deviation to NFPA 51 B-1971 to reduce the 35 foot zone for fire watch coverage based on NFPA 51 B-2009 due to coverings that limit the spread of fire sources during Shielded Metal Arc Welding (SMAW) and Gas Metal Arc Welding (GMAW).Page 2 of 2 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report L12-090 -TEMPORARY CHANGE FOR 2B REACTOR RECIRCULATION FLOW CONTROL VALVE OPERATION WITH FAILED LVDT/RVDT Description of Activity: The proposed activity is a compensatory action to provide an alternate method of re-positioning the 2B Reactor Recirculation (RR) Flow Control Valve (FCV), as a result of a degraded or nonconforming condition, caused by a failure of the 2B RR FCV Linear Variable Differential Transformer (LVDT) and Rotary Variable Differential Transformer (RVDT) position feedback sensors, rendering the 2B RR FCV position feedback loop inoperable.
The 2B RR FCV will be operated in an Open Loop mode due to loss of this position feedback.
This is a change from the original system configuration which is Closed Loop configuration.
UFSAR section G.1.2.2 recognizes the system configuration as using active valve position feedback (i.e., Closed Loop for valve position control), as well as other locations in the Safety Analysis Report (SAR) which recognize the position control loop as having valve position feedback.
This requires modifications to the control system logic and Operator Actions.Summary of Conclusion for the Activity's 50.59 Review: The proposed activity involves an alternate method of re-positioning the 2B RR Flow Control Valve in the event that both of the position feedback sensors (RVDT and LVDT) have failed due to inaccessible hardware malfunctions.
The 2B RR HPU (both B1 and B2 HPU subloop) will be placed in motion inhibit status, or "System Lockup". This will be accomplished by changes to the existing AC70 controller configurations and by jumpering the feedback control loop.The review accordingly concluded that this revision to the design bases: " Does not result in more than a minimal increase the frequency or consequences any accident or transient." Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.o Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L12-106 -REVISE DESIGN ANALYSES FOR A UHS TEMPERATURE OF 107 OF Description of Activity: The current Technical Specification Bases 3.7.3 and UFSAR Section 9.2.6 define a temperature limit of 101.25 OF for the cooling water supplied to the plant during normal operating conditions to ensure that, during design basis conditions, the temperature of the water will permit safe shutdown and cool down of the reactors.
The limit is set such that the temperature does not exceed 104 OF when the UHS is subjected to the worst case historical weather consistent with Reg. Guide 1.27, Rev. 1 requirements.
The temperature of 104 OF represents the maximum temperature of cooling water supplied to the plant during design basis accident conditions.
Page 1 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report The proposed activity and its supporting analyses evaluate plant equipment for an increased post accident inlet cooling water temperature; increased from 104 OF to 107 OF. EC 388666 evaluates plant equipment at predicted UHS maximum temperatures/conditions and revises affected design analyses, procedures, UFSAR sections, TS Bases, and TRM Sections for the increase in UHS temperature.
Summary of Conclusion for the Activity's 50.59 Review: The proposed activity is being performed to demonstrate the heat removal capabilities for heat exchangers/coolers credited with supporting safe shutdown of the reactor at the higher UHS temperature of 107 OF. This is being done to support a future License Amendment Request to revise (increase) the Technical Specification Limit of 101.25 OF, which would be evaluated with a separate activity.The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient.
- Does not result in more a minimal increase in the likelihood or consequences of a malfunction." Does not create a possibility of a different type of accident or transient." Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered." Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L1 2-229 -SAT TR242 OPEN PHASE DETECTION PROTECTIVE RELAY CIRCUIT INSTALLATION (UNIT 2)Description of Activity: The proposed activity will add a new protective relaying scheme to isolate the Unit 2 System Auxiliary Transformer (SAT) 242 upon detection of an open or loss of phase upstream of the SAT. The new protective relaying is an addition to the existing protective devices which isolate the SAT.Summary of Conclusion for the Activity's 50.59 Review: Since the proposed activity is considered an enhancement of the preferred (offsite) power source to protect the Class 1 E system from a condition that is outside the current design and licensing basis for the plant, the failure of the new system to perform its intended function of isolating the unit's SAT upon detection of an open or loss of phase upstream of a transformer does not adversely affect any UFSAR-described design function.The proposed activity does not adversely affect the SAT capacity or the existing automatic and manual switching capabilities involving the normal, reserve, standby, or emergency feeds to the 4kV or 6.9kV buses. The proposed activity does not adversely affect the existing equipment protection, including protection from overcurrent, undervoltage, or degraded voltage conditions.
Page 2 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report There is no adverse impact on UFSAR-described design functions for the 125VDC, control room annunciator, or HVAC systems. The proposed activity will not adversely affect how the UFSAR-described functions for these systems are performed or controlled.
The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient.
- Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result." Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L12-241 -TEMPORARY SUBSTITUTION OF LS-1 FOR LS-2 OF INBOARD MSIV 1 B21-F022A (RPS B1 SCRAM CHANNEL)Description of Activity: This design change (EC 391664) temporarily connects limit switch LS-1 of inboard MSIV 1 B21 -F022A to perform the function of the failed RPS limit switch LS-2 in the RPS B1 Trip Channel for the MSIV "Not Fully Open" Scram function.
The RPS B1 Trip Channel for the MSIV "Not Fully Open" Scram function will be rewired for the Unit 1 Inboard MSIV 1 B21 -F022A to change the circuit from the LS-2 limit switch, contacts G-H, to the LS-1 limit switch, contacts C-D. This will be accomplished by disconnecting the LS-2 limit switch cable at a junction box outside containment, and disconnecting the cable connected to the LS-1 limit switch circuit at containment electrical penetration E-9. The limit switch LS-1 circuit will then be connected to the RPS circuit by connecting a temporary cable conductor between the RPS circuit and the E-9 penetration terminal block of the LS-1 switch.The LS-1 switch provides an input into the process computer (ID1447) for the 1A Inboard MSIV position.
The LS-1 switch opens at the necessary MSIV position to meet the Tech Spec 3.3.1.1 requirement for the RPS channel. An additional process computer input (ID1448) for MSIV position which functions off of Limit switch LS-3 will also be disabled as a result of disconnecting and removing the cable from the E-9 penetration for the installation of the temporary cable.Summary of Conclusion for the Activity's 50.59 Review: Currently, the limit switch LS-2 of the Unit 1 Inboard MSIV 1 B21 -F022A is inoperable because the switch did not trip the associated RPS channel during quarterly surveillance.
This condition results in the RPS B1 channel for the "MSIV not fully open" as inoperable.
This requires that the RPS B1 "MSIV not full open" channel be placed in a tripped condition until this RPS channel is returned to operable in accordance with Technical Specification 3.3.1.1. Substituting the LS-1 limit switch will allow the RPS channel to be declared operable and the channel trip removed.Page 3 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient." Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result." Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L1 3-002 -NEDC-33106P REVISION 4 GEXL97 CORRELATION FOR ATRIUM-10 FUEL Description of Activity: The proposed activity is to apply the GEXL97 critical power correlation described in GNF document NEDC-33106P Revision 4 at LaSalle Station. The use of this correlation will support application of the GEXL97 correlation for ATRIUM-10 fuel. The critical power correlation is described in UFSAR Section 4.4.2.2.1 and is used to ensure that during all normal operating and anticipated operational occurrences at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling.Summary of Conclusion for the Activity's 50.59 Review: Review of the proposed activity has determined that GEXL97 as documented in NEDC-33106P Revision 4 produces essentially the same results as the analysis of record that has been reviewed and approved by the NRC for LaSalle 1 Cycle 11 and documented in the associated SE. The implementation of the GEXL97 correlation does not result in a departure from a method of evaluation described in the UFSAR used in establishing the design basis or in the safety analysis.The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L13-016 -REMOVE CHECK VALVE AIR ACTUATORS FROM 2E12-FO41A/B/C.
2E12-F050A/B, 2E22-F005 AND 2E21-F006 (UNIT 2)Description of Activity: This Engineering Change will remove parts of the air actuator test assembly from ECCS and shutdown cooling check valves 2E12-FO41A/B/C, 2E12-FO50A/B, 2E21 -F006, and 2E22-F005.
This change supports the check valves being manually stroked for maintenance and testing.Page 4 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report Summary of Conclusion for the Activity's 50.59 Review: This activity involves the removal of the air actuators, previously used to perform manual outage related tests and maintenance activates with the ECCS and shutdown cooling check valves.The tests are now performed with an equivalent manual method and the air operators are no longer required.
The air operator had no UFSAR design function to support the operation of the ECCS systems. The change does not impact the UFSAR design function of the HPCS, LPCS, RHR, and LPCI systems or the check valves. The RCS isolation function and configuration of the valves as described in UFSAR Section 6.2.4.2.1 will not be changed. The change does not impact the UFSAR performance requirements of the ECCS systems. The check valves and associated piping remain qualified in accordance with the applicable UFSAR design codes.The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient." Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L13-017 -APPLICATION OF TRACG04P VERSION 4.2.69.0 FOR OPRM SETPOINT DETERMINATION AT LASALLE Description of Activity: This activity addresses the use of the General Electric Hitachi (GEH) advanced, multi-purpose NSSS thermal-hydraulic transient code TRACG04P Version 4.2.69.0, for the purpose of determining the Oscillation Power Range Monitor (OPRM) setpoints for LaSalle County Station.Summary of Conclusion for the Activity's 50.59 Review: GEH benchmarking analyses confirm that TRACG04P produces DIVOM curves that are slightly more conservative than those produced by TRACG02A.
Therefore the use of TRACG04P Version 4.2.69.0 does not constitute a departure from a method of evaluation described in the UFSAR, and TRACG04P can be used to support the determination of cycle specific OPRM setpoints without prior NRC approval.Page 5 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report L13-074 -REMOVE CHECK VALVE AIR ACTUATORS FROM 1 E12-F041 AB/C. 1E12-F050AB. 1E22-F005 AND 1E21-F006 (UNIT 1)Description of Activity: This Engineering Change will remove parts of the air actuator test assembly from ECCS and shutdown cooling check valves 1 E12-FO41A/B/C, 1 E12-FO50A/B, 1 E21-F006, and 1 E22-F005.This change supports the check valves being manually stroked for maintenance and testing.Summary of Conclusion for the Activity's 50.59 Review: This activity involves the removal of the air actuators, previously used to perform manual outage related tests and maintenance activities with the ECCS and shutdown cooling check valves.The tests are now performed with an equivalent manual method and the air operators are no longer required.
The air operator had no UFSAR design function to support the operation of the ECCS systems. The change does not impact the UFSAR design function of the HPCS, LPCS, RHR, and LPCI systems or the check valves. The RCS isolation function and configuration of the valves as described in UFSAR Section 6.2.4.2.1 will not be changed. The change does not impact the UFSAR performance requirements of the ECCS systems. The check valves and associated piping remain qualified in accordance with the applicable UFSAR design codes.The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient.
- Does not result in more a minimal increase in the likelihood or consequences of a malfunction." Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.Li 3-084 -SAT TR142 OPEN PHASE DETECTION PROTECTIVE RELAY CIRCUIT INSTALLATION (UNIT 1)Description of Activity: The proposed activity will add a new protective relaying scheme to isolate the Unit 1 System Auxiliary Transformer (SAT) 142 upon detection of an open or loss of phase upstream of the SAT. The new protective relaying is an addition to the existing protective devices which isolate the SAT.Summary of Conclusion for the Activity's 50.59 Review: Since the proposed activity is considered an enhancement of the preferred (offsite) power source to protect the Class 1 E system from a condition that is outside the current design and licensing basis for the plant, the failure of the new system to perform its intended function of isolating the unit's SAT upon detection of an open or loss of phase upstream of a transformer does not adversely affect any UFSAR-described design function.Page 6 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report The proposed activity does not adversely affect the SAT capacity or the existing automatic and manual switching capabilities involving the normal, reserve, standby, or emergency feeds to the 4kV or 6.9kV buses. The proposed activity does not adversely affect the existing equipment protection, including protection from overcurrent, undervoltage, or degraded voltage conditions.
There is no adverse impact on UFSAR-described design functions for the 125VDC, control room annunciator, or HVAC systems. The proposed activity will not adversely affect how the UFSAR-described functions for these systems are performed or controlled.
The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient.
- Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
- Does not create a possibility for a malfunction with a different result." Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L13-117 -ULTIMATE HEAT SINK FISH MORTALITY EVALUATION Description of Activity: The proposed activity is a design change that will incorporate the Ultimate Heat Sink (UHS) Fish Mortality Evaluation performed under EC 390948 into the existing design basis for the UHS and shad net. This change also includes a change to UFSAR Section 2.5.5.2.5, to add a discussion on the affects of dead shad on the shad net within the CSCS Pond during a design basis accident and the actions taken to prevent accumulation of shad on the net and a procedure revision to LOA-DIKE-001, "Lake Dike Damage Failure." Summary of Conclusion for the Activity's 50.59 Review: EC 394134 and Calculation L-003842 document the evaluation of the effects of fish and vegetation on the shad net. The evaluation found that the quantity of fish seeking refuge within the UHS would have a negligible effect to the UHS effective volume. The shad net components are capable of withstanding the associated forces acting on the components during a dike break and fish kill event. It was also determined that a breach concurrent with a DBA will result in thermal loading of the UHS causing the fish remaining in the UHS to perish during the 30 day coping period.The review accordingly concluded that this revision to the design bases: " Does not result in more than a minimal increase the frequency or consequences any accident or transient.
- Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
- Does not create a possibility of a different type of accident or transient.
Page 7 of 8 ATTACHMENT C LaSalle 10 CFR 50.59 Evaluation Summary Report* Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.L13-124 -CHEMICAL SEPARATION BUILDINGS FOR CHEMICAL INJECTION SYSTEMS Description of Activity: This activity is a modification that replaces the existing Lake Screen House chemical feed pump house with two new chemical feed pump houses provided by NALCO. One pump house is primarily dedicated to the pumping and handling of sodium hypochlorite, referred to as the Sodium Hypochlorite Feed Building (SHFB). The other pump house is dedicated to the pumping and handling of acids, referred to as the Acid Feed Building (AFB).Summary of Conclusion for the Activfty's 50.59 Review: The physical changes being made by this activity decrease the likelihood of a toxic gas release which could challenge Control Room Habitability.
This EC does not increase the volume of any chemical stored. The injection points and the chemical feed functions remain the same. The additional power required from the existing Lake Screen House Auxiliary Power system does not adversely affect the non-safety related 480V AC system's ability to fulfill its described design functions.
The proposed activity does not involve any tests or experiments where SSCs are utilized or controlled in a manner that is outside of their bounds of design. All affected SSCs are designed for the application.
This modification does not affect the Control Room Area Filtration or Ventilation AC Systems as discussed in the Technical Specifications and TRM. The Technical Specification described Control Room Envelope Habitability Program is not affected by this change.The review accordingly concluded that this revision to the design bases:* Does not result in more than a minimal increase the frequency or consequences any accident or transient.
o Does not result in more a minimal increase in the likelihood or consequences of a malfunction.
o Does not create a possibility of a different type of accident or transient.
o Does not create a possibility for a malfunction with a different result.* Does not result in any design basis limit for a fission product barrier (DBLFPB) being exceeded or altered.* Does not constitute a departure from UFSAR described method of evaluation.
The 50.59 Evaluation concluded that the activity could be implemented without prior NRC approval.Page 8 of 8 ATTACHMENT D LaSalle 10 CFR 72.48 Evaluation Summary Report All 10 CFR 72.48 reviews performed from the initiation of dry cask storage activities at LaSalle County Station through December 31, 2013 were screenings.
There were no 10 CFR 72.48 Evaluations performed during this period.Page 1 of 1 ATTACHMENT E OSM Directory Structure Exelon Nuclear -LaSalle County Station UFSAR Rev 20, April 2014 -Proprietary Directory Path File Name Sensitivity Level E:\001 LAS UFSAR Rev. 20 000 List of Effective Pages.pdf 538 KB Publicly Available E:\001 LAS UFSAR Rev. 20 001 Chap 01 Introduction.pdf 289 KB Publicly Available E:\001 LAS UFSAR Rev. 20 002 Chap 02 Site Characteristics.pdf 2513 KB Publicly Available E:\001 LAS UFSAR Rev. 20 003 Chap 02 Figures Part 1 of 2.pdf 21294 KB Publicly Available E:\001 LAS UFSAR Rev. 20 004 Chap 02 Figures Part 2 of 2.pdf 36761 KB Publicly Available E:\001 LAS UFSAR Rev. 20 005 Chap 03 Design of Struct Comp, Equip.pdf 37313 KB Publicly Available E:\001 LAS UFSAR Rev. 20 006 Chap 04 Reactor.pdf 10933 KB Publicly Available E:\001 LAS UFSAR Rev. 20 007 Chap 05 Reactor Coolant.pdf 6022 KB Publicly Available E:\001 LAS UFSAR Rev. 20 008 Chap 06 Eng Safety Features.pdf 13504 KB Publicly Available E:\001 LAS UFSAR Rev. 20 009 Chap 07 Instr and Control Sys.pdf 8079 KB Publicly Available E:\001 LAS UFSAR Rev. 20 010 Chap 08 Electric Power.pdf 3895 KB Publicly Available E:\001 LAS UFSAR Rev. 20 011 Chap 09 Auxiliary Systems.pdf 1436 KB Publicly Available E:\001 LAS UFSAR Rev. 20 012 Chap 09 Figures Part 1 of 14.pdf 1731 KB Publicly Available E:\001 LAS UFSAR Rev. 20 013 Chap 09 Figures Part 2 of 14.pdf 48349 KB Publicly Available E:\001 LAS UFSAR Rev. 20 014 Chap 09 Figures Part 3 of 14.pdf 44237 KB Publicly Available E:\001 LAS UFSAR Rev. 20 015 Chap 09 Figures Part 4 of 14.pdf 42613 KB Publicly Available E:\001 LAS UFSAFI Rev. 20 016 Chap 09 Figures Part 5 of 14.pdf 49266 KB Publicly Available E:\001 LAS UFSAR Rev. 20 017 Chap 09 Figures Part 6 of 14.pdf 44842 KB Publicly Available E:\001 LAS UFSAR Rev. 20 018 Chap 09 Figures Part 7 of 14.pdf 46374 KB Publicly Available E:\001 LAS UFSAR Rev. 20 019 Chap 09 Figures Part 8 of 14.pdf 44981 KB Publicly Available E:\001 LAS UFSAR Rev. 20 020 Chap 09 Figures Part 9 of 14.pdf 36328 KB Publicly Available E:\001 LAS UFSAR Rev. 20 021 Chap 09 Figures Part 10 of 14.pdf 40374 KB Publicly Available E:\001 LAS UFSAR Rev. 20 022 Chap 09 Figures Part 11 of 14.pdf 47990 KB Publicly Available E:\001 LAS UFSAR Rev. 20 023 Chap 09 Figures Part 12 of 14.pdf 19609 KB Publicly Available E:\001 LAS UFSAR Rev. 20 024 Chap 09 Figures Part 13 of 14.pdf 20752 KB Publicly Available E:\001 LAS UFSAR Rev. 20 025 Chap 09 Figures Part 14 of 14.pdf 2953 KB Publicly Available E:\001 LAS UFSAR Rev. 20 026 Chap 10 Steam and Power Conv.pdf 1424 KB Publicly Available E:\001 LAS UFSAR Rev. 20 027 Chap 11 Radioactive Waste Mgmt.pdf 1170 KB Publicly Available E:\001 LAS UFSAR Rev. 20 028 Chap 12 Radiation Protection.pdf 11265 KB Publicly Available E:\001 LAS UFSAR Rev. 20 029 Chap 13 Conduct of Operations.pdf 488 KB Publicly Available E:\001 LAS UFSAR Rev. 20 030 Chap 14 Initial Test Program.pdf 48 KB Publicly Available E:\001 LAS UFSAR Rev. 20 031 Chap 15 Accident Analysis.pdf 7062 KB Publicly Available E:\001 LAS UFSAR Rev. 20 032 Chap 16 Technical Specifications.pdf 42 KB Publicly Available E:\001 LAS UFSAR Rev. 20 033 Chap 17 Quality Assurance.pdf 53 KB Publicly Available E:\001 LAS UFSAR Rev. 20 034 Appendices.pdf 10051 KB Publicly Available E:\002 LAS TRM -Proprietary 001 LAS TRM -Proprietary.pdf 7606 KB Proprietary E:\003 LAS Tech Spec Bases 001 LAS Tech Spec Bases.pdf 2091 KB Publicly Available E:\004 LAS FPR Rev. 6 001 LAS FPR Rev. 6.pdf 11050 KB Publicly Available Page 1 of 2 ATTACHMENT E OSM Directory Structure Exelon Nuclear -LaSalle County Station UFSAR Rev 20, April 2014 -Non-Proprietary Directory Path File Name Size Sensitivity Level E:\001 LAS UFSAR Rev. 20 000 List of Effective Pages.pdf 538 KB Publicly Available E:\001 LAS UFSAR Rev. 20 001 Chap 01 Introduction.pdf 289 KB Publicly Available E:\001 LAS UFSAR Rev. 20 002 Chap 02 Site Characteristics.pdf 2513 KB Publicly Available E:\001 LAS UFSAR Rev. 20 003 Chap 02 Figures Part 1 of 2.pdf 21294 KB Publicly Available E:\001 LAS UFSAR Rev. 20 004 Chap 02 Figures Part 2 of 2.pdf 36761 KB Publicly Available E:\001 LAS UFSAR Rev. 20 005 Chap 03 Design of Struct Comp, Equip.pdf 37313 KB Publicly Available E:\001 LAS UFSAR Rev. 20 006 Chap 04 Reactor.pdf 10933 KB Publicly Available E:\001 LAS UFSAR Rev. 20 007 Chap 05 Reactor Coolant.pdf 6022 KB Publicly Available E:\001 LAS UFSAR Rev. 20 008 Chap 06 Eng Safety Features.pdf 13504 KB Publicly Available E:\001 LAS UFSAR Rev. 20 009 Chap 07 Instr and Control Sys.pdf 8079 KB Publicly Available E:\001 LAS UFSAR Rev. 20 010 Chap 08 Electric Power.pdf 3895 KB Publicly Available E:\001 LAS UFSAR Rev. 20 011 Chap 09 Auxiliary Systems.pdf 1436 KB Publicly Available E:\001 LAS UFSAR Rev. 20 012 Chap 09 Figures Part 1 of 14.pdf 1731 KB Publicly Available E:\001 LAS UFSAR Rev. 20 013 Chap 09 Figures Part 2 of 14.pdf 48349 KB Publicly Available E:\001 LAS UFSAR Rev. 20 014 Chap 09 Figures Part 3 of 14.pdf 44237 KB Publicly Available E:\001 LAS UFSAR Rev. 20 015 Chap 09 Figures Part 4 of 14.pdf 42613 KB Publicly Available E:\001 LAS UFSAR Rev. 20 016 Chap 09 Figures Part 5 of 14.pdf 49266 KB Publicly Available E:\001 LAS UFSAR Rev. 20 017 Chap 09 Figures Part 6 of 14.pdf 44842 KB Publicly Available E:\001 LAS UFSAR Rev. 20 018 Chap 09 Figures Part 7 of 14.pdf 46374 KB Publicly Available E:\001 LAS UFSAR Rev. 20 019 Chap 09 Figures Part 8 of 14.pdf 44981 KB Publicly Available E:\001 LAS UFSAR Rev. 20 020 Chap 09 Figures Part 9 of 14.pdf 36328 KB Publicly Available E:\001 LAS UFSAR Rev. 20 021 Chap 09 Figures Part 10 of 14.pdf 40374 KB Publicly Available E:\001 LAS UFSAR Rev. 20 022 Chap 09 Figures Part 11 of 14.pdf 47990 KB Publicly Available E:\001 LAS UFSAR Rev. 20 023 Chap 09 Figures Part 12 of 14.pdf 19609 KB Publicly Available E:\001 LAS UFSAR Rev. 20 024 Chap 09 Figures Part 13 of 14.pdf 20752 KB Publicly Available E:\001 LAS UFSAR Rev. 20 025 Chap 09 Figures Part 14 of 14.pdf 2953 KB Publicly Available E:\001 LAS UFSAR Rev. 20 026 Chap 10 Steam and Power Conv.pdf 1424 KB Publicly Available E:\001 LAS UFSAR Rev. 20 027 Chap 11 Radioactive Waste Mgmt.pdf 1170 KB Publicly Available E:\001 LAS UFSAR Rev. 20 028 Chap 12 Radiation Protection.pdf 11265 KB Publicly Available E:\001 LAS UFSAR Rev. 20 029 Chap 13 Conduct of Operations.pdf 488 KB Publicly Available E:\001 LAS UFSAR Rev. 20 030 Chap 14 Initial Test Program.pdf 48 KB Publicly Available E:\001 LAS UFSAR Rev. 20 031 Chap 15 Accident Analysis.pdf 7062 KB Publicly Available E:\001 LAS UFSAR Rev. 20 032 Chap 16 Technical Specifications.pdf 42 KB Publicly Available E:\001 LAS UFSAR Rev. 20 033 Chap 17 Quality Assurance.pdf 53 KB Publicly Available E:\001 LAS UFSAR Rev. 20 034 Appendices.pdf 10051 KB Publicly Available E:\002 LAS TRM -Non-Prop 001 LAS TRM -Non-Proprietary.pdf 6140 KB Publicly Available E:\003 LAS Tech Spec Bases 001 LAS Tech Spec Bases.pdf 2091 KB Publicly Available E:\004 LAS FPR Rev. 6 001 LAS FPR Rev. 6.pdf 11050 KB Publicly Available Page 2 of 2