Text

Submittal of Revision 23 to Updated Final Safety Analysis Report, Revision 8 to Fire Protection Report, Revised Technical Requirements Manual and Revised Technical Specification Bases
	ML18117A016
Person / Time
Site:	LaSalle
Issue date:	04/11/2018
From:	; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML18117A015	List: ML18117A016; ML18117A018; ML18117A019; ML18117A021; ML18117A022; ML18117A023; ML18117A026; ML18117A027; ML18117A028; ML18117A029; ML18117A036; ML18117A037; ML18117A040; ML18117A041; ML18117A042; ML18117A043; ML18117A047; ML20038A147; ML20038A157; ML20038A172; ML20038A178; ML20038A192; ML20038A200; ML20038A201; ML20038A205; ML20038A215; ML20038A218; ML20038A232; ML20038A244; ML20038A247; RS-18-044, Revised Technical Specification Bases;
References
	RS-18-044
	Download: ML18117A016 (18)
	v • d • e

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~- Exelon Generation RS-18-044 April 11, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 LaSalle County Station, Units 1 and 2 10 CFR 50.71(e)(4) 10 CFR 50.59( d)(2) 10 CFR 72.48(d)(2) 10 CFR 54.37(b)

Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373, 50-374, and 72-70

Subject:

LaSalle County Station Updated Final Safety Analysis Report (UFSAR), Revision 23 and Fire Protection Report (FPR), Revision 8 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 23 to the Updated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 8 to the Fire Protection Report (FPR), and summaries of evaluations conducted pursuant to 10 CFR 50.59, "Changes, tests, and experiments," 10 CFR 72.48, "Changes, tests, and experiments," and 10 CFR 54.37(b) "Additional records and recordkeeping requirements."

The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (e.g., Technical-Requirements Manual and Technical Specifications Bases). All UFSAR pages changed as a result of this update are clearly delineated with "Rev. 23, APRIL 2018" in the page footer.

One OSM is included in this submission. The OSM labeled, "Exelon Nuclear - LaSalle County Station UFSAR Rev. 23, April 2018," contains the following components:

001 002 003 004 LAS UFSAR Rev. 23.pdf, 695 megabytes LAS FPR Rev. 8.pdf, 9.87 megabytes LAS TRM, 5.28 megabytes LAS Tech Spec Bases.pdf, 1.79 megabytes J-o£*S frtJb {o

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April 11, 2018 U.S. Nuclear Regulatory Commission Page 3 Attachment A provides a brief summary of the changes incorporated into UFSAR, Revision 23.

Attachment B provides a brief summary of the changes incorporated into the FPR, Revision 8.

Attachment C provides the summary report pursuant to 50.59.

Attachment D provides the summary report pursuant to 72.48.

Attachment E provides the 54.37(b) Aging Management Review Summary.

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

As required by 1 O CFR 50.71 (e)(2)(i), I, Manager-Licensing Programs, certify that to the best of my knowledge, the information contained in the enclosures and attachments to this letter accurately reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provisions of 1 O 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.

Respectfully, g7~M<~

Dominic M. Imburgia Manager - Licensing Programs

Enclosure:

OSM - LaSalle County Station - UFSAR Revision 23, FPR Revision 8 Attachments:

Attachment A, "LaSalle County Station UFSAR Revision 23 Change Summary Report" Attachment B, "LaSalle County Station FPR Revision 8 Change Summary Report" Attachment C, "LaSalle County Station 1 O CFR 50.59 Evaluation Summary Report" Attachment D, "LaSalle.County.Station to CFR 72.48 Evaluation Summary Beport" Attachment E, "LaSalle County Station 10 CFR 54.37(b) Aging Management Review Summary" Attachment F, "OSM Directory Structure" cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station NRC Project Manager, NRR - LaSalle County Station

LUCR-0401 ATTACHMENT A LaSalle County Station U FSAR Revision 23 Change Summary Report Revised Pool Swell Analysis Revised Sections 6.2.1.1.3.3.1 and 6.2.7 to update pool swell response profiles for a DBA LOCA after re-analyzation with a new methodology.

LUCR-0400 Seismic Category 1 Tornado Missile Protection by design calculations.

Revised Section 3.5.1.4 to list tornado generated missiles which LaSalle County Station Seismic Category I structures are adequately protected against by design and evaluation.

LUCR-0398 LaSalle CADA Revision to AST Revised Sections 15.4.9.2, 15.4.9.3.1, 15.4.9.5, 15.4.10, 15.7.4.5, Tables 15.4-6 to 15.4-15, and Table 15.7-21 to incorporate CADA analysis which changes methodology to use Alternative Source Term (AST).

LUCR-0396 VY Cooler Flow Update per EC 620533 Revised Section 9.2.1.1.1, Page 9.2-2, to change cubicle cooling coil flows for southeast cubicle area cooler to read 80 gpm and northeast cubicle area cooler to read 66.5 gpm for Unit 1 and 87.8 gpm for Unit 2.

LUCR-0395 LaSalle Unit 2 Reload Cycle 16 Revised Figures 4.1, 4.2, 6.3, Sections 4.1, 4.2, 4.3, 4.4, 4.6, 6.3, 15.2, 15.6, 15.8, 15.1 O, 15.A, Tables 4.2, 4.4, 6.3, and Table of Contents 4.0, 6.0, 15.0 to support FCP EC 404167 for LaSalle Unit 2 Cycle 17. Changes include removal of ATRIUM-10 fuel from the Unit 2 core and the change to the GS3 methodology tor the stability analysis. Additional changes were made to Section 6.3 per NF-M-102.

LUCR-0394 NGET (PAT & RWT) extension from 2 years to SAT approved frequency.

Revised UFSAR Section 13.2 to extend the frequency of Radiation Worker Training (RWT) and Plant Access Training (PAT) from 2 years to a frequency deemed acceptable by the systematic approach to training (SAT) process to support a more effective training cycle without reducing the margin to safety.

LUCR-0393

. Update Section 10.4:6:2 to allow operation of 7 GP Beds during HWCU planned and planned system outages.

Revised Section 10.4.6.2, Page 10.4-14, to allow the operation of seven condensate polisher (CP) beds for a period of up to seven days during a planned or unplanned RWCU outage to maintain chemistry coolant parameters.

Page 1 of 5

LUCR-0392 ATTACHMENT A LaSalle County Station UFSAR Revision 23 Change Summary Report Alternate Drain of Dry~ell Drains Systems Revised Section 5.2.5.1, Page 5.2-40, and Section 6.2.6.1.m, Page 6.2-75, to allow the use of an alternate method of draining the floor drain sumps instead of using the floor drain sump pumps.

Sections 5.2.5.1 and 6.2.6.1 reference pump activity for the drain systems. Due to the installation of ECs 348182 and 348186, Section 5.2.5.1 revised drain pump activities to drain activities and Section 6.2.6.1 added drain down as an option to lower water levels of the floor and equipment drain sumps.

LUCR-0390 Replace seismic monitoring system with new system that conforms to RG 1.12, RG 1.166, and RG 1.167.

Revised Section 3. 7 and Appendix B to document the changes made by replacirg the seismic monitoring system with a new seismic monitoring system that conforms to Regulatory Guides 1.12 Rev. 2, 1.166 Rev. 0, and 1.167 Rev. 0.

LUCR-0389 Change analytical limit for fire main steam line low pressure from ~ 825 to ~ 820.

Revised Tables 7.3-2 (Page 3 of 3) to change analytical or design basis limit for Main Steamline Pressure Low to read ~ 820 psig. Also revised Section 15.1.3 (Page 15.1-9) and Section 15.1.5 (Page 15.1:-16), to add an explanation of the GEH Evaluation 002N7147-RO.

LUCR-0388 UFSAR 4.2.3.1.3 Update in support of CA 246496-13.

Revised Section 4.2.3.1.3 to document three jet pump plug pads were lost during L2R15; the three lost jet pump pads will be evaluated on a cycle specific basis and the results will be documented in the Core Operating Limits Report (COLA) since efforts to recover the plugs were unsuccessful during L2R15 and L2R16.

LUCR-0386 Category I Masonry Wall Clarifications Revised Page 3.C-3 and 3.C-5 of Attachment 3.C to clarify that a 1.67 overstress factor is used for applicable load cases in accordance with Table 3.C-1 referenced in Section 3.C.3.

LUCR-0385 Change 40 Year Profile to 60 Year Profile per License Renewal SER.

Revised Sections 3.1.2, 3.11, Table 3.11-27, 3.11-27, and Figure 3.11 series to incorporate 60-year license renewal approved by the NRC, reformatted LOCA temperature profile, and updated time/temperature.

LUCR-0384 Incorporate LSCS License Renewal Application Appendix A into the existing UFSAR as the new Appendix P.

Revised UFSAR Sections 3.8.1.7.3.1.4, 3.9.1.1.1, 3.9.3.1.2.4, 4.3.2.8, 5.2.2.4.2.2.1.1, 5.2.2.4.2.2.2.1, 5.4.4.4 and Tables 3.9-24 and 5.2-4, added the new Appendix P, and revised the last page of the Master Table of Contents.

Page 2 of 5

LUCR-0383 ATTACHMENT A LaSalle County Station UFSAR Revision 23 Change Summary Report Revision to extend the frequency of Radiation Worker Training (RWT) and Plant Access Training (PAT) from every year to every 2 years.

Revised UFSAR Sections 13.2 to extend the frequency of Radiation Worker Training (RWT) and Plant Access Training (PAT) from every year to every 2 years.

LUCR-0381 Revision to update partial length rod burnup approval for operation above 62 GWD/MTU.

Revised UFSAR Appendix B, Sections 15.6.5.5.14, 15.6.7, 15.7.4.5, and 15.7.6, and Table 15.7-21 to reflect NRC approval for ATRIUM-10 partial length rod to exceed RG 1.183 burnup limit of 62 GWD/MTU.

LUCR-0380 Remove inaccurate revision bar from UFSAR Table 8.3-3.

Revised UFSAR Table 8.3-3 "Diesel-Generator Ratings" to remove inaccurate revision bar. This revision bar is an administrative error caused by a revision to the previous page (Table 8.3-2).

LUCR-0379 Change "continuous" in the fourth paragraph to "2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months " I

Revised UFSAR Appendix B Page B.0-11 to state the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating of the diesel generator is greater than the maximum coincidental steady-state loads requiring power at any time.

LUCR-0378 Correction of site boundary property lines Revised Figures 2.1-2, 2.1-3, 2.4-3, 2.5-3, 2.5-41, and 8.2-2 to accurately depict property boundary right-of-way for the makeup and blowdown water pipelines as a result of various property sales and purchases.

LUCR-0377 Update description of Main Steam Line Process Radiation Monitors Revised UFSAR Section 15.4.9.2 to clarify main steam line process radiation monitors no longer have a scram or isolation function.

LUCR-0376 Revise Unit 2 Drywell Equipment Hatch Barrel Platform Revised Chapter 3, Section 8, Figure 3.8-34, to include the new drywell equipment hatch platform structure Which accommodates loadsassociated with Unit 2 Reactor Recirculation pump motor replacement.

LUCR-0375 Correction to UFSAR description of SBLC function.

Revised Section 9.3.5.2 to correct errors when implementing AST (LUCR-216) to include all functions of Standby Liquid Control (SBLC) System which includes keeping the reactor from going critical in the event not enough control rods can be inserted in the reactor core to accomplish shutdown and buffering the suppression pool during a LOCA to prevent elemental iodine re-evolution.

Page 3 of 5

LUCR-0374 ATTACHMENT A LaSalle County Station UFSAR Revision 23 Change Summary Report Reference update to support FCP revision Revised UFSAR Section Pages 4.1-20, 4.2-52, 4.3-11, 4.3-14, 4.3-18, 4.4-25, 4.4-28, 5.2-4, 5.2-51, 5.2-52, 15.0-14, 15.1-7, 15.1-15, 15.2-45, 15.3-16, 15.4-27, 15.4-32, 15.7-29, 15.A-11, and 15.10-2 to support L2C16 mid-cycle implementation of TRACG AOO and GS3.

LUCR-0373 Plant to Offsite Communications Revised UFSAR Section 9.5.2.2.6 description of plant-to-offsite communications to state Plant to Offsite Radio communications is provided as described in the Exelon Emergency Plan Annex for LaSalle Station and the LaSalle Station Security Plan. Revised Section 9.5.2.3 to" state plant to offsite communications are governed by LaSalle Station's Emergency Plan Annex and the Station Security Plan.

LUCR-0372 Unit 2 ERVR for RBCCW Revised Section 6.2.4.2.2, "Evaluation Against GDC 56," Page 6.2-61, and Section 7.A.3.2.1, Conformance to IEEE 279-1971, "Criteria for Protection Systems for Nuclear Power Generation Stations," Page 7.A.3-42, for applicability of RBCCW PCIV Logic to Unit 1 and Unit 2.

LUCR-0371 Connection between HPCS and CST is abandoned. Suppression pool is the only coolant source for HPCS Revised U FSAR Section 6.1.1.2 Rev 14 in reference to AR 02653895 to state that connection between HPCS and CST is abandoned by placing a blind flange in line and there is no administrative controlled flowpath between HPCS and CST; therefore, the suppression pool is the only normal coolant source for HPCS.

LUCR-0370 Revision to UFSAR Sections 7.7.14.1.*2.2, 11.3.2.1.1.5.3, 11.3.2.1.1.9, and 11.5.2.1.2 Revised UFSAR Sections 7. 7.14.1.2.2, 11.3.2.1.1.5.3, 11.3.2.1.1.9, and 11.5.2.1.2 to change off-gas vent valves from failed closed position to failed open position to prevent single point vulnerabilities.

LUCR-0369 Battery enclosure requirement Revised'UFSAR Figure 6:2-31, Section 9.5.1:2.2, and Tables 6.2~21, 6.2~31, and 75.-1 to add new Hardened Containment Vent System (HCVS) Primary Containment Isolation Valves (PC IVs) 2PC009A and 2PC010A and batteries.

LUCR-0368 Revision to UFSAR Section 15.9.5 Revised UFSAR Section 15.9.5 to add reference to 1997 supplemental safety evaluation report (SER) discussing Class 1 E battery sizing requirements for station blackout.

Page 4 of 5

LUCR-0367 ATTACHMENT A LaSalle County Station UFSAR Revision 23 Change Summary Report Revision to UFSAR Section 6.3.2.2.5 Revised UFSAR Section 6.3.2.2.5 to add description of TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation," implementation and fix incorrect reference to GL 2008-001.

LUCR-0366 Removal of Unit 2 Hydrogen Water Chemistry System trips Revised Table 5.4-2 to remove trips for Hydrogen Flow, Hydrogen Pressure, Hydrogen Injection Module Water Flow Differential Pressure, and Isolation Monitors In Test. Revised Section 5.4.15.1.2 to remove the sentence "Automatic isolation is provided to prevent hydrogen injection when no condensate flow is detected."

LUCR-0363 Exempting components from Appendix J Local Leak Rate Testing Revised UFSAR Table 6.2-21 to remove Local Leak Rate Testing for valves which meet the exclusion criteria due to qualified water seals.

LUCR-0358 Revision to UFSAR Table 6.2-21 Notes 28 and 44 Revised UFSAR Table 6.2-21 Notes 28 and 44 to correct inaccurate SRP references.

LUCR-0354 Install flushing check valves on SDV Hydrolyzing Ports Revised section 4.6.1.1.2.4.2.4, page 4.6-11, to add the wording "check valves and" to a sentence describing the hydrolyzing port of the scram discharge volume (SDV) heading piping.

LUCR-0350 Figure updates Unit 1 Equipment Hatch. Drywell Revised Chapter 3, Section 8, Figure 3.8-34, to include the new drywall.equipment hatch platform structure which accommodates loads associated with Unit 1 Reactor Recirculation pump motor replacement.

LUCR-0337 Unit 2 4kV Bus Transfer Logic Modifications for an Open Phase Condition Concurrent with a LOCA Revised UFSAR Section 8.3.1.1.2 to describe Unit 1 and Unit 2 4kV Bus Transfer Logic Modifications for an Open Phase Condition Concurrent with a LOCA and a loss of the SAT.

LUCR-0279 Revision to UFSAR Sections 6.3.2.2.3. 6.3.2.2.4. 7.3.1.2.1.10, 7.3.1.2.3.9.

7.3.1.2.4.9, Table 6.2-21 Sheet 34 of 49, and Figure 6.2-31 Revised UFSAR Sections 6.3.2.2.3, 6.3.2.2.4, 7.3.1.2.1.10, 7.3.1.2.3.9, 7.3.1.2.4.9, Table 6.2-21 Sheet 34 of 49, and Figure 6.2-31 to delete removal of the air actuators on ECCS check valves 1 (2)E12-F041 A/B/C, 1(2)E12-F050A/8, 1 (2)E22-F005 and 1 (2)E21-F006 and the installation of the new manual locking.

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I I

LF2016-01 LF2016-02 LS2016-03 LF2017-01 ATTACHMENT B LaSalle County Station FPR Revision 8 Change Summary Report LF2016-01 revises LaSalle FPR Section H.3.5.17, Page H.3-118 for Fire Zone 5B13. EC 392353 installs new common 125VDC HCVS batteries in Fire Zone 5B13. Tlie FPR is being revised to include the new batteries in the discussion of a credible fire under the Design Basis Fire subheading of Fire Zone 5813.

LF2016-02 revises LaSalle FPR H.3.4.18 Page H.3-89 due to installation of intumescent firestop collars at ceiling penetrations of Fire Zone 505 where combustible i in is used er EC 406591.

LF2016-03 revises the FPR 5-2, Page 5-23, LaSalle FPR NFPA Code Deviation Summary Matrix for N FPA-1 O, for fire extinguishers in high radiation areas to be ins ected on a 24-month schedule.

LF2017-01 revises the Fire Protection Report to make the following changes as summarized below:

1. Table H.4-50 (sheet 1 of 8), change "RHR Instrument cable 1 NB075" to "MSIV 1 B21-F028A cable 1 NB075"

2. Table H.4-50 (sheet 7 of 8), delete duplicate entry "RHR Instrument cable 1 NB075"

3. Table H.4-54 (sheet 1 of 7), change "RHR Instrument cable 1 NB075" to "MSIV 1 B21-F028A cable 1 NB075"

4. Table H.4-54 (sheet 7 of 7), delete duplicate entry "RHR Instrument cable 1 NB075"

5. Table H.4-60 (sheet 1 of 9), change "RHR Instrument cable 1 NB075" to "MSIV 1 B21-F028A cable 1 N8075"

6. Table H.4-60 (sheet 7 of 9), delete duplicate entry "RHR Instrument cable 1 NB075"

7. Table H.4-63 (sheet 1 of 7), change "RHR Instrument cable 1 NB075" to "MSIV 1 B21-F028A cable 1 NB075"

8. Table H.4-69 (sheet 1 of 9), change "RHR Instrument cable 1 NB075" to "MSIV 1 B21-F028A cable 1 NB075"

9. Table H.4-69 (sheet 9 of 9), delete duplicate entry "AHR Instrument cable 1 NB075" Page 1 of 1

ATTACHMENT C LaSalle County Station 1 O CFR 50.59 Evaluation Summary Report L 16-159 - INCREASED FLOW THROUGH REACTOR WATER CLEANUP Description of Activity:

The proposed activity will validate the Reactor Water Cleanup (RWCU) system has the capability of reaching 10% above current design flow as evaluated in Evaluation No. 2014-09820, "Evaluation of RWCU System Normal Flow Increase." Evaluation No. 2014-09829, Revision O, was performed by Sargent and Lundy (S&L) and approved by SEAG Letter 14-000110. The evaluation determined a 10% RWCU flow increase produced acceptable results of the parameters with no adverse consequences. The recommendation to perform a flow capacity test to ensure the current control valve position and design (trim) are adequate to meet the desired increase, will be conducted under special test procedure, LST-2015-002, Revision 0, "Increased Flow Through Reactor Water Cleanup." The RWCU system will be operated normally with an additional 10% flow pumped through the system, which includes the filter demineralizers. LST-2015-002 will validate the RWCU system has the capability of reaching 10% above current design flow prior to making any permanent design changes for increased RWCU flow to improve collective radiation exposure (CRE).

Summary of Conclusion for the Activity's 50.59 Review:

The proposed activity involves increasing the flow through RWCU to validate the system is capable of reaching 10% above current design flow. This activity proves the increase in flow will not adversely affect the RWCU system prior to making any permanent design changes to improve CRE. The RWCU system will be operated normally with only an additional 10% flow being pumped through the system including the filter demineralizers which is within the current design of the system as evaluated by Evaluation No. 2014-09820 Revision 0. The activity will not adversely affect changes to system and area temperatures nor will it require changes to thermal power other than normal monitoring because of the small changes to heat balance inputs.

The review accordingly concluded that this flow modification:

Does not result in more than a minimal increase in the frequency or consequences of 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 ditf erent 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 NRG approval.

Page 1 of 7

r ATTACHMENT C LaSalle County Station 1 O CFR 50.59 Evaluation Summary Report L 17 DEFEAT HWC H2 SUPPLY HIGH PRESSURE TRIP Description of Activity:

The proposed activity involves eliminating the Hydrogen Water Chemistry (HWC) High Pressure trip function by installing a jumper across the normally closed contact of High Pressure Switch 2P73-N105 inside Panel 2P73-P100. The jumper installation will also bypass the Unit 2 control room alarm. However, the high pressure alarm condition for the alarm function will remain available through the Unit 1 High Pressure Switch 1 P73-N105.

Summary of Conclusion for the Activity's 50.59 Review:

The proposed activity to replace the HWC automatic trip with alarm and manual operator actions identified above will not alter the function of this system as described in UFSAR 5.4.15.

The high pressure alarm condition for the alarm function is available from Unit 1 high pressure switch 1 P73-N105. The activity will not cause the hydrogen concentration in off-gas to reach the lower explosive limit, and UFSAR 15.7.1.1.1 states a hydrogen detonation is not considered as a possible failure mode for the off-gas system because the equipment and piping are designed to contain any hydrogen-oxygen detonation. The activity does not change the

- function, design basis, or normal operation of the HWC system as described in the UFSAR. The activity will improve the availability and reliability of the HWC system by eliminating spurious trips. The HWC system does not perform safety-related or post-accident function.

The review accordingly concluded that eliminating the HWC trip:

Does not result in more than a minimal increase in the frequency or consequences of 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 NRG,

approval.

Page 2 of 7

ATTACHMENTC.

LaSalle County Station 1 O CFR 50.59 Evaluation Summary Report L17-19-RIVER SCREEN HOUSE AND LAKE ABNORMAL Description of Activity:

The proposed activity will defeat the lake make up pumps trip caused by traveling screen HI-HI D/P during extreme cold weather. Differential level switches OLDS-WLOO?, servicing OWL01 FA screen, and OLDS-WL028, servicing OWL01 FB screen, provide trip functions for the OWL01 PA(B) and OWL01 PC lake makeup pumps, respectively. This protects the traveling screens when ice or debris on the screens will not collapse the screens. The trip function is defeated by opening the installed test switches located on switchgear 041 that are in series with the trip coils from the HI-HI screen D/P switch. A non-minimum staff operator is required to be present at the river screen house while the trips are defeated. All remaining alarm and trip functions associated with the Lake Make-Up pumps will not affected by this change.

Summary of Conclusion for the Activity's 50.59 Review:

The proposed activity to remove the Lake Make-Up Pump HI-HI screen DIP switch pressure trip by replacing the automatic action with a manual operator action does not change the function, design basis, or normal operation of the Lake Make-Up system as described in the UFSAR.

The proposed activity will improve the availability and reliability of the Lake Make-Up system by eliminating spurious trips. The Lake Make-Up system also does not perform safety-related or post-accident function. The proposed activity does not result in a change that would cause any system parameter to change and there is no postulated failure related to this system.

The review accordingly concluded that this revision to the design bases:

Does not result in more than a minimal increase in the frequency or consequences of 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 NRG approval.

Page 3 of 7

ATTACHMENT C LaSalle County Station 1 O CFR 50.59 Evaluation Summary Report L 17 SEISMIC MONITORING INSTRUMENTATION UPGRADE Description of Activity:

The proposed activity is to upgrade the seismic instrumentation to comply with Regulatory Guide (RG) 1.12, Revision 2, RG 1.166, and RG 1.167 which utilizes Cumulative Absolute Velocity (CAV) as an input to Operating Basis Earthquake (OBE) exceedance. The CAV has a more precise correlation to structural damage compared to the current design spectra utilized to measure OBE exceedance. Replacing the existing seismic system with a state-of-the-art system which measure the CAV could eliminate an unnecessary plant shutdown caused by high frequency, low energy earthquakes, which does not result in structural damage. This modification will replace the central recorder and all accelerometers with a new Syscom seismic monitoring system. The recorders wil_l transmit seismic data to a new Network Control Center,

(NCC). The data will be analyzed to determine whether an earthquake has exceeded the QBE.

The new seismic monitoring system will meet all criteria outlined RG 1.12, Revision 2, RG 1.166 and RG 1.167. The modified seismic monitoring system will continue to provide the necessary alarms and data to assist the plant staff in performing required actions following a seismic event.

Failures within the seismic monitoring system will also be alarmed to help ensure operability requirements for seismic monitoring equipment are maintained.

Summary of Conclusion for the Activity's 50.59 Review:

The proposed activity installs a modified seismic monitoring system which determines the appropriate seismic response during an earthquake event. The actions taken to operate the new seismic monitoring equipment is similar to the existing equipment. Existing control room alarms will be retained and actuate when the seismic monitoring system is triggered by a seismic event resulting in an OBE exceedance. The installation of the new Syscom seismic monitoring equipment will allow for an improved assessment of the effects of a seismic event in order to determine the appropriate station response, including the determination of whether the plant should be shut down, and will avoid unnecessary shutdowns from high frequency, low energy earthquakes. The proposed activity does not involve a change to a structure, system, and component (SSC) that adversely affects a UFSAR described design function and does not change the seismic design response spectra of UFSAR Section 3.7.1.1 used to evaluate functional requirements of any SSC important to safety.

The review accordingly conch,ided that this revision to the design bases:

Does not result in more than a minimal increase in the frequency or consequences of 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.

Page 4 of 7

ATTACHMENT C LaSalle County Station 10 CFR 50.59 Evaluation Summary Report L 17 REPLACEMENT SOR PRESSURE SWITCH FOR MAIN STEAM LINE LOW PRESSURE Description of Activity:

The proposed activity documents a design change which allows the use of replacement static-o-ring (SOR) Model 29N6-B45-U1-C1 A-JJTTNQ for obsolete SOR Model 9N6-B45-NX-C1 A-JJTTX6 installed in Main Steam Line (MSL) Low Pressure Group I Isolation function, 1 (2)B21-N015A, B, C, and D. This activity includes revising the MSL Low Pressure main steam isolation valve (MSIV) Isolation Setpoint Analysis, NED-1-EIC-0206, and MSL Pressure - Low Analytical Limit detailed in UFSAR Table 7.3-2. The Analytical limit change from 825 psig to 820 psig results in a 4 psi margin reduction to the 700 psia Safety Limit but the minimum margin for all cases evaluated remains greater than 15 psi. The replacement pressure switch model performs the same fqnction and meets the same environmental and seismic qualifications as the existing pressure switch model.

Summary of Conclusion for the Activity's 50.59 Review:

The proposed activity to use an alternate SOR Pressure Switch Model for MSL Low Pressure Isolation function does not alter the design function or interaction of any SSC as described in the UFSAR and the replacement will continue to perform the same function as the current SOR Pressure Switch Model. The proposed activity to change the setpoint analysis does not affect any analyses that support the design bases or safety analysis. In addition, the proposed activity does not involve a test or experiment that adversely impacts any design function described in the UFSAR.