LaSalle, Units 1 & 2, Submittal of Updated Final Safety ... · Updated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 6 to ... accordance with 10

V 4300 Winfield RoadWarrenville, 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 50.5910 CFR 72.48

April 11, 2014

U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555

LaSalle County Station, Units 1 and 2Facility Operating License Nos. NPF-1 1 and NPF-1 8NRC 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 ofreports," paragraph (e)(4), Exelon Generation Company (EGC), LLC submits Revision 20 to theUpdated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 6 tothe Fire Protection Report (FPR) and summaries of evaluations conducted pursuant to10 CFR 50.59, "Changes, tests, and experiments" and 10 CFR 72.48. "Changes, tests, andexperiments."

The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, includingdocuments incorporated by reference (e.g., Technical Requirements Manual and TechnicalSpecifications Bases). All UFSAR pages changed as a result of this update are clearly delineatedwith "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 toGNF-A, and is supported by a signed affidavit from the owner of the information. The affidavit, whichis provided within the applicable document, sets forth the basis on which the information may bewithheld from public disclosure by the NRC, and addresses with specificity the considerations listed inparagraph (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 inaccordance 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 CountyStation UFSAR Rev. 20, April 2014- Proprietary," contains the following components:

001 LAS UFSAR Rev. 20.pdf, 649 megabytes, publicly available002 LAS TRM - Proprietary.pdf, 7.42 megabytes, proprietary003 LAS Tech Spec Bases.pdf, 2.04 megabytes, publicly available004 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 11,2014U. S. Nuclear Regulatory CommissionPage 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 available002 LAS TRM - NP.pdf, 5.99 megabytes, publicly available003 LAS Tech Spec Bases.pdf, 2.04 megabytes, publicly available004 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 wereevaluated in accordance with the requirements of 10 CFR 50.59, and were implemented incalendar years 2012 and 2013. Attachment D provides the initial LaSalle County Stationsummary report pursuant to 72.48(d)(2). This report indicates that no 10 CFR 72.48evaluations were performed from the initiation of dry cask storage activities through the end of2013. 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 presentschanges made since the previous submittal necessary to reflect information and analysessubmitted to the NRC or prepared pursuant to NRC requirements, and changes made underthe provisions of 10 CFR 50.59 and 10 CFR 72.48.

There are no commitments in this letter. Should you have any questions concerning thissubmittal, please contact Amy Hambly at (630) 657-2808.

Reset ly

Patrick R. SimpsonManager - 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 IIINRC 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 toSeismic 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 exclusioncriteria.

LUCR-0220 Revision to UFSAR Table 12.3-17

Revised UFSAR Table 12.3-17 to transition the drywell continuous air monitors particulate alarmpoint 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 caskwell to include an identification of the low-level waste (LLW) storage racks and compactionequipment 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 thermoluminescentdosimeter (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 descriptionregarding 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 updateinformation 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 perEngineering 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 radbypass logic.

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ATTACHMENT A


Revision to UFSAR Appendix G Section G.2.1.1.1LUCR-0255

Revised UFSAR Appendix G, Section G.2.1.1.1 to document the potential of an alternate insulationmaterial 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.


Revised UFSAR Table 3.2-1 to clarify that Low-Pressure Core Spray System (LPCS) valvesbeyond the outermost isolation valves and cables with a safety function have an electricalclassification of 1 E.

LUCR-0260 Revision to Multiple UFSAR Sections to Support Increasing MaximumAllowed 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-Ininserts in all accessible locations in the Unit 2 Spent Fuel Pool was complete.

LUCR-0262 Revision to Multiple UFSAR Sections to Correct Editorial andTypographical 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 tosingle 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 toGeneric Letter (GL) 2008-01 for managing gas accumulation.


Revised UFSAR Table 5.2-9 to correct a discrepancy between the Safety Relief Valve (SRV) flowcapacities identified in the table and the nameplate flow capacities. The UFSAR is revised to reflectthe nameplate flow capacities, which are slightly higher.

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ATTACHMENT A


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 LevelWaste 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 andB31.1 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 generatornameplate 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 theEDG protective-Trip Bypass Test will be controlled under the surveillance frequency controlprogram.


Revised UFSAR Table 8.3-2 to add open phase detection relays as protective devices for the ESF4160 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 shadnet.

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 fromcalculations performed due to issues noted during Fukushima flooding walkdowns. This changealso 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 removalof the air actuators on Emergency Core Cooling System (ECCS) check valves and the installationof 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 WaterClean Up (RWCU) differential flow signals during heatup and cooldown.

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ATTACHMENT A


LUCR-0275 Revision to UFSAR Sections 11.4.1.1. Tables 11.4-1 and 11.4-2. Sections11.4.1.4 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 todescribe use of the Interim Radwaste Storage Facility (IRSF) building to store low-level radioactivewaste 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 inLaSalle 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 andTable 5.2-12

Revised UFSAR Sections to reflect removal of Unit 1 120 degree surveillance capsule.


Revised UFSAR Table 8.3-2 to add SAT protective relay description, including loss of phase forUnit 1.


Revised UFSAR Sections 3.3.2.2.3 and 3.5.2.1 to clarify/enhance the discussion of the protection ofsafety-related systems and components from tornado missiles.


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 andDC system for the 138 kV switchyard, and to show 138 kV connections to Kickapoo Creeksubstation.

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ATTACHMENT A


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 inLaSalle Unit 2. This analysis was performed by GEH in conjunction with the new fuel introductionfor 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 1and 2 buses 141Y(241Y) and 142Y(241Y) is considered to be inoperable if these buses are beingfed from the unit onsite power source through UAT 141 (241) during unit operation.


Revised UFSAR Sections 4.1.2.1.1 and 4.1.3.2 to add discussion of the Marathon Ultra ControlBlade.

LUCR-0295 Revision to UFSAR Sections 6.3. 6.B. 15.2. 15.6. 15.A. Figure 6.3. Tables 6.3and 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 incorporateGEH LOCA Analysis for ATRIUM-10 fuel for Unit 1 and remove AREVA LOCA Analysis forATRIUM-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 cyclespecific analysis performed by AREVA.

Page 5 of 5

ATTACHMENT B

LaSalle FPR Revision 6 Change Summary Report

FDRP DescriptioniLF2012-001 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). Theactivity 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 and4E2-2 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 arenot in the following Fire Zones:a) Fire Zone 4D3 Table H.4-57- Cables 1 RH419, 1 RH501, 1 RH502,

1AP123, 1AP124, 1AP128, 1AP129, 1AP135, 1AP136, 1AP170,1AP171, 1AP443, 1DC034, 1DG082, 1DG083, 1DG124, 1NB356and 1 R1021.

b) Fire Zone 4E1-1 Table H.4-59- 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.4-67- 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 R1098and 1 RI 198.

d) Fire Zone 4F3 Table H.4-69- 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 thusprotected.

4) Revised the Safe Shutdown Analysis (SSA), to credit ADS Division I inFire Zone 3H3 (Section H.4.2.19) instead of ADS Division 2 which ispart 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 removestatements about fire detectors being in the 24/48 volt battery rooms.

6) Revised the Fire Protection Report Section 5, Code DeviationSummary Matrix sections 90A-2 and 803-12 to remove statementsabout Class I filters since UL 900 will no longer be classifying filters asClass I based on EC 388391 Revision 0.

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ATTACHMENT B

LaSalle FPR Revision 6 Change Summary Report

FDRP F Description13-001 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 and1 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 activityrevised the Fire Protection Report (FPR) to credit recorder 1 LR-CM028in fire zones that contain indicator 1 LI-CM032. Both of theseinstruments are shown on FPR Table H.4-108 and both instruments arelocated in the Main Control Room (MCR). Both instruments are part ofthe 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 alsorevised the Fire Protection Report Table H.3-1 to remove the Main SteamIsolation Valve Leakage Control System (MSIV-LCS) that has beenabandoned in-place on Unit 1 and deleted on Unit 2 as documented inUFSAR Chapter 6.7. Reference: FPR Table H.3-1 page 8 and UFSARChapter 3.11.1.2, page 3.11-12.

LF2013-004 LF2013-004 revised Fire Protection Report Section 5, page 5.2-63 to allowan NFPA deviation to NFPA 51 B-1971 to reduce the 35 foot zone for firewatch coverage based on NFPA 51 B-2009 due to coverings that limit thespread of fire sources during Shielded Metal Arc Welding (SMAW) and GasMetal Arc Welding (GMAW).

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ATTACHMENT C

LaSalle 10 CFR 50.59 Evaluation Summary Report

L12-090 - TEMPORARY CHANGE FOR 2B REACTOR RECIRCULATION FLOW CONTROLVALVE OPERATION WITH FAILED LVDT/RVDT

Description of Activity:The proposed activity is a compensatory action to provide an alternate method of re-positioningthe 2B Reactor Recirculation (RR) Flow Control Valve (FCV), as a result of a degraded ornonconforming condition, caused by a failure of the 2B RR FCV Linear Variable DifferentialTransformer (LVDT) and Rotary Variable Differential Transformer (RVDT) position feedbacksensors, rendering the 2B RR FCV position feedback loop inoperable. The 2B RR FCV will beoperated in an Open Loop mode due to loss of this position feedback. This is a change fromthe original system configuration which is Closed Loop configuration. UFSAR section G.1.2.2recognizes the system configuration as using active valve position feedback (i.e., Closed Loopfor valve position control), as well as other locations in the Safety Analysis Report (SAR) whichrecognize the position control loop as having valve position feedback. This requiresmodifications 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 ControlValve in the event that both of the position feedback sensors (RVDT and LVDT) have failed dueto inaccessible hardware malfunctions. The 2B RR HPU (both B1 and B2 HPU subloop) will beplaced in motion inhibit status, or "System Lockup". This will be accomplished by changes tothe 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 NRCapproval.

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 temperaturelimit of 101.25 OF for the cooling water supplied to the plant during normal operating conditionsto ensure that, during design basis conditions, the temperature of the water will permit safeshutdown and cool down of the reactors. The limit is set such that the temperature does notexceed 104 OF when the UHS is subjected to the worst case historical weather consistent withReg. Guide 1.27, Rev. 1 requirements. The temperature of 104 OF represents the maximumtemperature of cooling water supplied to the plant during design basis accident conditions.

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ATTACHMENT C


The proposed activity and its supporting analyses evaluate plant equipment for an increasedpost accident inlet cooling water temperature; increased from 104 OF to 107 OF. EC 388666evaluates plant equipment at predicted UHS maximum temperatures/conditions and revisesaffected design analyses, procedures, UFSAR sections, TS Bases, and TRM Sections for theincrease 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 heatexchangers/coolers credited with supporting safe shutdown of the reactor at the higher UHStemperature of 107 OF. This is being done to support a future License Amendment Request torevise (increase) the Technical Specification Limit of 101.25 OF, which would be evaluated witha 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.


L1 2-229 - SAT TR242 OPEN PHASE DETECTION PROTECTIVE RELAY CIRCUITINSTALLATION (UNIT 2)

Description of Activity:The proposed activity will add a new protective relaying scheme to isolate the Unit 2 SystemAuxiliary Transformer (SAT) 242 upon detection of an open or loss of phase upstream of theSAT. The new protective relaying is an addition to the existing protective devices which isolatethe SAT.

Summary of Conclusion for the Activity's 50.59 Review:Since the proposed activity is considered an enhancement of the preferred (offsite) powersource to protect the Class 1 E system from a condition that is outside the current design andlicensing basis for the plant, the failure of the new system to perform its intended function ofisolating the unit's SAT upon detection of an open or loss of phase upstream of a transformerdoes not adversely affect any UFSAR-described design function.

The proposed activity does not adversely affect the SAT capacity or the existing automatic andmanual switching capabilities involving the normal, reserve, standby, or emergency feeds to the4kV or 6.9kV buses. The proposed activity does not adversely affect the existing equipmentprotection, including protection from overcurrent, undervoltage, or degraded voltage conditions.

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ATTACHMENT C


There is no adverse impact on UFSAR-described design functions for the 125VDC, controlroom annunciator, or HVAC systems. The proposed activity will not adversely affect how theUFSAR-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


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.


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 forthe MSIV "Not Fully Open" Scram function. The RPS B1 Trip Channel for the MSIV "Not FullyOpen" Scram function will be rewired for the Unit 1 Inboard MSIV 1 B21 -F022A to change thecircuit from the LS-2 limit switch, contacts G-H, to the LS-1 limit switch, contacts C-D. This willbe accomplished by disconnecting the LS-2 limit switch cable at a junction box outsidecontainment, and disconnecting the cable connected to the LS-1 limit switch circuit atcontainment electrical penetration E-9. The limit switch LS-1 circuit will then be connected tothe RPS circuit by connecting a temporary cable conductor between the RPS circuit and the E-9penetration terminal block of the LS-1 switch.

The LS-1 switch provides an input into the process computer (ID1447) for the 1A Inboard MSIVposition. The LS-1 switch opens at the necessary MSIV position to meet the Tech Spec 3.3.1.1requirement for the RPS channel. An additional process computer input (ID1448) for MSIVposition which functions off of Limit switch LS-3 will also be disabled as a result of disconnectingand 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 becausethe switch did not trip the associated RPS channel during quarterly surveillance. This conditionresults in the RPS B1 channel for the "MSIV not fully open" as inoperable. This requires thatthe RPS B1 "MSIV not full open" channel be placed in a tripped condition until this RPS channelis returned to operable in accordance with Technical Specification 3.3.1.1. Substituting the LS-1limit switch will allow the RPS channel to be declared operable and the channel trip removed.

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ATTACHMENT C


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


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



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 GNFdocument NEDC-33106P Revision 4 at LaSalle Station. The use of this correlation will supportapplication of the GEXL97 correlation for ATRIUM-10 fuel. The critical power correlation isdescribed in UFSAR Section 4.4.2.2.1 and is used to ensure that during all normal operatingand anticipated operational occurrences at least 99.9% of the fuel rods in the core would not beexpected 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-33106PRevision 4 produces essentially the same results as the analysis of record that has beenreviewed and approved by the NRC for LaSalle 1 Cycle 11 and documented in the associatedSE. The implementation of the GEXL97 correlation does not result in a departure from amethod of evaluation described in the UFSAR used in establishing the design basis or in thesafety analysis.


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 andshutdown 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.

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ATTACHMENT C


Summary of Conclusion for the Activity's 50.59 Review:This activity involves the removal of the air actuators, previously used to perform manual outagerelated 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 nolonger required. The air operator had no UFSAR design function to support the operation of theECCS 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 ofthe valves as described in UFSAR Section 6.2.4.2.1 will not be changed. The change does notimpact the UFSAR performance requirements of the ECCS systems. The check valves andassociated piping remain qualified in accordance with the applicable UFSAR design codes.



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



L13-017 - APPLICATION OF TRACG04P VERSION 4.2.69.0 FOR OPRM SETPOINTDETERMINATION AT LASALLE

Description of Activity:This activity addresses the use of the General Electric Hitachi (GEH) advanced, multi-purposeNSSS thermal-hydraulic transient code TRACG04P Version 4.2.69.0, for the purpose ofdetermining 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 slightlymore conservative than those produced by TRACG02A. Therefore the use of TRACG04PVersion 4.2.69.0 does not constitute a departure from a method of evaluation described in theUFSAR, and TRACG04P can be used to support the determination of cycle specific OPRMsetpoints without prior NRC approval.

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ATTACHMENT C


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 andshutdown 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 outagerelated 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 nolonger required. The air operator had no UFSAR design function to support the operation of theECCS 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 ofthe valves as described in UFSAR Section 6.2.4.2.1 will not be changed. The change does notimpact the UFSAR performance requirements of the ECCS systems. The check valves andassociated piping remain qualified in accordance with the applicable UFSAR design codes.



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



Li 3-084 - SAT TR142 OPEN PHASE DETECTION PROTECTIVE RELAY CIRCUITINSTALLATION (UNIT 1)

Description of Activity:The proposed activity will add a new protective relaying scheme to isolate the Unit 1 SystemAuxiliary Transformer (SAT) 142 upon detection of an open or loss of phase upstream of theSAT. The new protective relaying is an addition to the existing protective devices which isolatethe SAT.

Summary of Conclusion for the Activity's 50.59 Review:Since the proposed activity is considered an enhancement of the preferred (offsite) powersource to protect the Class 1 E system from a condition that is outside the current design andlicensing basis for the plant, the failure of the new system to perform its intended function ofisolating the unit's SAT upon detection of an open or loss of phase upstream of a transformerdoes not adversely affect any UFSAR-described design function.

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ATTACHMENT C


The proposed activity does not adversely affect the SAT capacity or the existing automatic andmanual switching capabilities involving the normal, reserve, standby, or emergency feeds to the4kV or 6.9kV buses. The proposed activity does not adversely affect the existing equipmentprotection, including protection from overcurrent, undervoltage, or degraded voltage conditions.There is no adverse impact on UFSAR-described design functions for the 125VDC, controlroom annunciator, or HVAC systems. The proposed activity will not adversely affect how theUFSAR-described functions for these systems are performed or controlled.



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



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) FishMortality Evaluation performed under EC 390948 into the existing design basis for the UHS andshad net. This change also includes a change to UFSAR Section 2.5.5.2.5, to add a discussionon the affects of dead shad on the shad net within the CSCS Pond during a design basisaccident and the actions taken to prevent accumulation of shad on the net and a procedurerevision 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 andvegetation on the shad net. The evaluation found that the quantity of fish seeking refuge withinthe UHS would have a negligible effect to the UHS effective volume. The shad net componentsare capable of withstanding the associated forces acting on the components during a dike breakand fish kill event. It was also determined that a breach concurrent with a DBA will result inthermal loading of the UHS causing the fish remaining in the UHS to perish during the 30 daycoping 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


malfunction.• Does not create a possibility of a different type of accident or transient.

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ATTACHMENT C


* 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



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 pumphouse with two new chemical feed pump houses provided by NALCO. One pump house isprimarily dedicated to the pumping and handling of sodium hypochlorite, referred to as theSodium Hypochlorite Feed Building (SHFB). The other pump house is dedicated to thepumping 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 releasewhich could challenge Control Room Habitability. This EC does not increase the volume of anychemical stored. The injection points and the chemical feed functions remain the same. Theadditional power required from the existing Lake Screen House Auxiliary Power system doesnot adversely affect the non-safety related 480V AC system's ability to fulfill its described designfunctions. The proposed activity does not involve any tests or experiments where SSCs areutilized or controlled in a manner that is outside of their bounds of design. All affected SSCs aredesigned for the application. This modification does not affect the Control Room Area Filtrationor Ventilation AC Systems as discussed in the Technical Specifications and TRM. TheTechnical Specification described Control Room Envelope Habitability Program is not affectedby this change.


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



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ATTACHMENT D


All 10 CFR 72.48 reviews performed from the initiation of dry cask storage activities atLaSalle County Station through December 31, 2013 were screenings. There were no10 CFR 72.48 Evaluations performed during this period.

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ATTACHMENT E

OSM Directory Structure

Exelon Nuclear - LaSalle County Station UFSAR Rev 20, April 2014 - Proprietary

Directory Path File Name Size• Sensitivity Level

E:\001 LAS UFSAR Rev. 20 000 List of Effective Pages.pdf 538 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 001 Chap 01 Introduction.pdf 289 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 002 Chap 02 Site Characteristics.pdf 2513 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 003 Chap 02 Figures Part 1 of 2.pdf 21294 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 004 Chap 02 Figures Part 2 of 2.pdf 36761 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 005 Chap 03 Design of Struct Comp, Equip.pdf 37313 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 006 Chap 04 Reactor.pdf 10933 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 007 Chap 05 Reactor Coolant.pdf 6022 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 008 Chap 06 Eng Safety Features.pdf 13504 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 009 Chap 07 Instr and Control Sys.pdf 8079 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 010 Chap 08 Electric Power.pdf 3895 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 011 Chap 09 Auxiliary Systems.pdf 1436 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 012 Chap 09 Figures Part 1 of 14.pdf 1731 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 013 Chap 09 Figures Part 2 of 14.pdf 48349 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 014 Chap 09 Figures Part 3 of 14.pdf 44237 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 015 Chap 09 Figures Part 4 of 14.pdf 42613 KB Publicly AvailableE:\001 LAS UFSAFI Rev. 20 016 Chap 09 Figures Part 5 of 14.pdf 49266 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 017 Chap 09 Figures Part 6 of 14.pdf 44842 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 018 Chap 09 Figures Part 7 of 14.pdf 46374 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 019 Chap 09 Figures Part 8 of 14.pdf 44981 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 020 Chap 09 Figures Part 9 of 14.pdf 36328 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 021 Chap 09 Figures Part 10 of 14.pdf 40374 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 022 Chap 09 Figures Part 11 of 14.pdf 47990 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 023 Chap 09 Figures Part 12 of 14.pdf 19609 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 024 Chap 09 Figures Part 13 of 14.pdf 20752 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 025 Chap 09 Figures Part 14 of 14.pdf 2953 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 026 Chap 10 Steam and Power Conv.pdf 1424 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 027 Chap 11 Radioactive Waste Mgmt.pdf 1170 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 028 Chap 12 Radiation Protection.pdf 11265 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 029 Chap 13 Conduct of Operations.pdf 488 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 030 Chap 14 Initial Test Program.pdf 48 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 031 Chap 15 Accident Analysis.pdf 7062 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 032 Chap 16 Technical Specifications.pdf 42 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 033 Chap 17 Quality Assurance.pdf 53 KB Publicly AvailableE:\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

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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 AvailableE:\001 LAS UFSAR Rev. 20 001 Chap 01 Introduction.pdf 289 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 002 Chap 02 Site Characteristics.pdf 2513 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 003 Chap 02 Figures Part 1 of 2.pdf 21294 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 004 Chap 02 Figures Part 2 of 2.pdf 36761 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 005 Chap 03 Design of Struct Comp, Equip.pdf 37313 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 006 Chap 04 Reactor.pdf 10933 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 007 Chap 05 Reactor Coolant.pdf 6022 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 008 Chap 06 Eng Safety Features.pdf 13504 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 009 Chap 07 Instr and Control Sys.pdf 8079 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 010 Chap 08 Electric Power.pdf 3895 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 011 Chap 09 Auxiliary Systems.pdf 1436 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 012 Chap 09 Figures Part 1 of 14.pdf 1731 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 013 Chap 09 Figures Part 2 of 14.pdf 48349 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 014 Chap 09 Figures Part 3 of 14.pdf 44237 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 015 Chap 09 Figures Part 4 of 14.pdf 42613 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 016 Chap 09 Figures Part 5 of 14.pdf 49266 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 017 Chap 09 Figures Part 6 of 14.pdf 44842 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 018 Chap 09 Figures Part 7 of 14.pdf 46374 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 019 Chap 09 Figures Part 8 of 14.pdf 44981 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 020 Chap 09 Figures Part 9 of 14.pdf 36328 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 021 Chap 09 Figures Part 10 of 14.pdf 40374 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 022 Chap 09 Figures Part 11 of 14.pdf 47990 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 023 Chap 09 Figures Part 12 of 14.pdf 19609 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 024 Chap 09 Figures Part 13 of 14.pdf 20752 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 025 Chap 09 Figures Part 14 of 14.pdf 2953 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 026 Chap 10 Steam and Power Conv.pdf 1424 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 027 Chap 11 Radioactive Waste Mgmt.pdf 1170 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 028 Chap 12 Radiation Protection.pdf 11265 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 029 Chap 13 Conduct of Operations.pdf 488 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 030 Chap 14 Initial Test Program.pdf 48 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 031 Chap 15 Accident Analysis.pdf 7062 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 032 Chap 16 Technical Specifications.pdf 42 KB Publicly AvailableE:\001 LAS UFSAR Rev. 20 033 Chap 17 Quality Assurance.pdf 53 KB Publicly AvailableE:\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

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Documents

LaSalle, Units 1 & 2, Submittal of Updated Final Safety ... · Updated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 6 to ... accordance with 10