ML20111A245
| ML20111A245 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/13/2020 |
| From: | Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20111A244 | List:
|
| References | |
| RS-20-029 | |
| Download: ML20111A245 (17) | |
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RS-20-029 10 CFR 50.71 (e)(4) 10 CFR 50.59(d)(2) 10 CFR 72.48(d)(2) 10 CFR 54.37(b)
April 13, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 LaSalle County Station, Units 1 and 2 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 24 and Fire Protection Report (FPR), Revision 9 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 24 to the Updated Final Safety Analysis Report (UFSAR) for LaSalle County Station (LSCS), Revision 9 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 (TRM) and Technical Specifications Bases (TSB)). All UFSAR pages changed as a result of this update are clearly delineated with "Rev. 24, APRIL 2020" in the page footer.
One OSM is included in this submission. The OSM labeled, "Exelon Nuclear - LaSalle County Station UFSAR Rev. 24, April 2020," contains the following components:
- 001 LAS UFSAR Rev. 24.pdf, 687 megabytes (MB) 002 LAS FPR Rev. 9.pdf, 14.6 MB 003 LAS TRM.pdf, 4.98 MB 004 LAS TSB.pdf, 2.65 MB
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April 13, 2020 U.S. Nuclear Regulatory Commission Page2 Attachment A provides a brief summary of the changes incorporated into UFSAR, Revision 24.
Attachment B provides a brief summary of the changes incorporated into the FPR, Revision 9.
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 10 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 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.
Respectfully, Z2-P~
David M. Gullatt Director - Licensing
Enclosure:
OSM - LaSalle County Station - UFSAR Revision 24, FPR Revision 9 Attachments:
Attachment A, "LaSalle County Station UFSAR Revision 24 Change Summary Report" Attachment B, "LaSalle County Station FPR.Revision 9 Change Summary Report" Attachment C, "LaSalle County Station 10 CFR 50.59 Evaluation Summary Report" Attachment D, "LaSalle County Station 10 CFR 72.48 Evaluation Summary Report" 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
AITACHMENTA LaSalle County Station UFSAR Revision 24 Change Summary Report LUCR-0284 Addition of flow measuring instrumentation to Unit 1 and Unit 2 RHR pump seal coolers Revised Section 9.2 (pages 9.2-5, 9.2-6, and 9.2-8) to reflect Unit 1 and Unit 2 "A" and "B" RHR pump seal coolers have a flow measuring element installed, while the "C" RHR does not.
LUCR-0301 Update to reflect change of GC for MST dT alarm setpoint Revised Section 1.2.2.6.6, 5.2.5.1, and 5.2.5.1.2.a to specify main steamline tunnel alarms will assist with the identification of potential system issues instead of leakage <=5 gpm.
LUCR-0331 Revision to UFSAR Section 7.7.15.2.8 and Figure 7.7-15 Revised Figure 7.7-15 and Section 7.7.15.2.8 to remove Sump Leak Detection Timer figure due to the sump pump monitoring system description being controlled by plant design drawings and Passport data.
LUCR-0347 Add PCIV 1E12-480A and B Revised Section 3.8.2.5.2.2.1, 3.8.6, Table 6.2-21, and Table 6.2-28 to incorporate the primary FLEX strategy response to a Beyond Design Basis External Event.
LUCR-0361 Add Diesel Generator Corridor to Appendix J .
Revised Appendix Table J.2 to include the Unit 1 Diesel Generator Corridor to Plant Areas and Equipment Affected by MELB due to 1DG05A-4" was routed through the corridor.
LUCR-0391 Unit 1 Hardened Containment Vent System (HCVS) Valves Revised Table 6.2-21 Sheet 17, Table 6.2-28 Sheet 7, and Note 8 of Table 7.5-1 to reflect Unit 1 Hardened Containment Vent System Valves implementation.
LUCR-0399 Post LOCA Dose Calculation Revised Section 15.6.7, Table 15.6-28, and Table 15.6-29 to update Loss of Coolant Accident using Alternative Source Terms.
LUCR-'0402 Clarify that Single-Load Rejection, Full-Load Rejection, and Test-Mode Change-Over Test is controlled by SFCP Revised Appendix 8, page 8.0-9, and Section 3.1, page 3.1-15, to clarify Section 2.2. 7 "Single-Load Rejection Test," Section 2.2.8 "Full-Load Rejection Test," and Section 2.2.13 "Test Mode Change-Over Test" surveillance frequencies are controlled under the Surveillance Frequency Change Program (SFCP), in accordance with STI evaluation LA-16-07.
Page 1 of 5
ATTACHMENT A LaSalle County Station UFSAR Revision 24 Change Summary Report LUCR-0404 L1 R17 Reload Analysis Revi.sed Sections 4.1.5, 4.2.5, 4.3.4, 4.4.7, 5.2.2.1, 5.2.2.2.2.1, 5.2.6, 9.1.1.3, 9.1.2.1.3.1, 15.0.4, 15.0.11, 15.1.3, 15.1.5, 15.2.3A.2, 15.2.3A.3, 15.2.11, 15.3.5, 15.4.10, 15.6.7, 15.7.6, 15.A.2, and 15.A.6 to replace the ODYN code with TRACG-AOO, update GESTAR to Revision 24, clarify example language, and delete old information.
LUCR-0405 Install Anti-Vibration System (AVS) on Unit 1 Jet Pumps Revised Sections 3.9.5.1.8, 4.5.2.1, and Figure G.4.1-1 to add details for the inclusion of AVS hardware and remove details for certain auxiliary wedges.
LUCR-0406 Increase HPCS Room ambient accident temperature to 155°F.
Revised Table 3.11-8, Section 6.2, and Section 9.4.5.3.1.1 to change the HPCS Room ambient accident temperature to 155°F.
LUCR-0407 Incorporate Regulatory Guide 1.52 Revision 3 Revised Appendix B and Section 6.4 to update Regulatory Guide 1.52 conformance from Revision 2 to Revision 3.
LUCR-0408 Update UFSAR Appendix B to take exception to the monthly surveillance requirement.
Revised Appendix B to take exception to the monthly surveillance requirement to run ESF atmospheric cleanup units as stated in committed Regulatory Guide 1.52 Revision 3. The exception will change the monthly surveillance frequency to a frequency controlled by the surveillance frequency control program.
LUCR-0410 Upgrade Chem Overlab Area Fire Protection Panel OFP17J and Detectors The existing ionization detectors installed in the concealed cable space over the laboratories are obsolete. They are replaced with photoelectric detectors in accordance with EC 62320.
LUCR-0411 NSF Channel Material for GNF2 Fuel Assemblies for LaSalle.
Revised Section 4.2.2.6 and 4.2.5 to add licensing topical report for NSF material on channel designs for GNF2 fuel.
LUCR-0412 Change Section 15.6.4.2 sequence of events to point to Table 6.3-7.
Revised Section 15.6.4.2 to remove entire sequence of events regarding system operation after a main steam line break outside of containment and reference Table 6.3-7.
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ATTACHMENT A LaSalle County Station UFSAR Revision 24 Change Summary Report LUCR-0413 Editorial corrections associated with previously approved LUCR-385 incorporated UFSAR Revision 23 Editorial corrections associated with the incorporation of previously approved LUCR-385 in UFSAR Revision 23. Revised UFSAR Table 3.11-8, 3.11-9, 3.11-10, 3.11-14, 3.11-16 (Sheet
- 1 of 2), 3.11-16 {Sheet2 of 2), 3.11-17, 3.11-19 {Sheet 1 of 2), 3.11-20, 3.11-26 (Sheet 1 of 2), 3.11-27 (Sheet 1 of 2), 3.11-27 (Sheet 2 of 2), and 3.11-28.
LUCR-0414 Change Net Pressure Suction Head value for RWCU system design Revised Table 5.4-1 to indicate correct RWCU NPSH values for Unit 1 at 11.5 feet and Unit 2 at 11.1 feet.
LUCR-0415 Update Diesel Generator Lube Oil System Description Revised Section 9.5. 7.2 to clarify the function of the lubricating and soak-back oil system for the Emergency Diesel Generator.
LUCR-0416 Change Scram Insertion Test from every 120 days to 200 days.
Revised Section 3.9.4.4 to replace the online scram time testing frequency of "every 120 days of operation" with "in accordance with the frequency specified in Surveillance Frequency Control Program."
LUCR-0417 Re-routing of CSCS Pipe 2DG05A-4 Updating Appendix .J, Section 7.1.3.3.3, and Table J.2 for Re-routing of 2DG05A-4.
LUCR-0418 Abandon 1(2)D0024 valves in the closed position with power removed or remove valve Revised Section 9.5.4.3 to indicate that Fire Pump Fuel Oil Transfer Pump Suction Valves 1(2)D0024 are abandoned in place in the close position.
LUCR-0419 Revise UFSAR Table 6.2-2 to correct CSCS maximum temperature Revised Table 6.2-2 to reflect design service water (CSCS) maximum temperature of 107 degrees F.
LUCR-0420 Installation of temporary chiller and air handling unit on the Refuel Floor.
Revised Section 3.5.2.1, page 3.5-9a, Table 3.2-1, Sheet 18 to incorporate safety related equipment on the Refuel Floor and a new subsystem of the Reactor Building Ventilation System which provides cooling during forced helium dehydrator operations for Dry Cask Storage campaigns.
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ATTACHMENT A LaSalle County Station UFSAR Revision 24 Change Summary Report LUCR-0421 Incorporate Unit 2 Drywell Equipment Drain System (DW EDS) gravity drain Revised Section 7.7.11.2.2, page 7.7-79, and Section 7.7.15.2.8, pages 7.7-104 and 7.7-105 to incorporate the Unit 2 DWEDS Gravity Drain which serves as an alternate method of measuring DWEDS leakage.
LUCR-0424 Clarify licensing basis (Table 3.8-11) regarding concurrent seismic and crane lifted loads.
Revised Table 3.8-11 to clarify seismic loads do not act concurrently with crane lifted loads unless the lift is required to meet Single failure Proof criteria.
LUCR-0425 LaSalle Unit 2 Reload 17 Revised pages 4.1-20, 4.2-34, 4.2-52, 4.2-53, 4.3-18, 4.4-4, 4.4-28, 4.4-29, 15.0-8, 15.0-14, 15.1-15, 15.1-16, 15.3-16, 15.4-32, 15.4-34, 15.6-29, 15.7-29, 15.9-3, 15.9-10, 15.A-1.1, 15.C-1, and Table 6.3-2 (sheet 5) to incorporate Unit 2 license analyses under GESTAR Revision 26, remove jet pump plugs MCPR penalty, remove Atrium fuel discussion and incorporated a discussion of GNF2/GNF3, as all Atrium fuel has been discharged and GNF3 is inbound.
LUCR-0426 Replacement of Jet Pump Inlet Mixers with Previously Removed Inlet Mixers Revised Section 3.9.5.1.8 and 4.5.2.1 to specify several Unit 2 jet pump inlet mixers were replaced with the original design due to foreign material in L2R17.
LUCR-0427 Install a fourth station air compressor Section 9.2.8.2 (page 9.2-29), Section 9.3.1.2 (Page 9.3-2), and Figure 9.5-1 (page 9.3-2 and Figure 9.5-1 Sheet 25 (page 9.2-29).
LUCR-0428 Revise license basis for Tornado Missile protection Revised Section 3.5.2.1 page 3.5-9a, Section 3.5.2.2 page 3.5-10, and Section 3.5.4 page 3.5-13 to s1:1pdate the UFSAR to identify the TMP licensing basis, in accordance with 50.59 Evaluation L 19.:.159_
LUCR-0429 Update for current Unit 1 Core Reload Analysis, adoption of TSTF-564 Safety Limit MCPR. and update of Chapter 15 "Infrequent Event" categorization for lost parts capable of causing high percentage of flow orifice blockage.
Revised 4.1-20, 4.2-52, 4.2-53, 4.3-18, 5.2-51, 15.0-2, 15.0-4, 15.0-5, 15.0-7, 15.0-14, 15.1-15, 15.2-45, 15.3-16, 15.4-32, 15.6-29, 15.7-29, 1_5.A-11, and Table 15.A-1. The majority of changes are normal updates based on new cycle-specific documents. Also, various changes to the location of the Safety Limit MCPR are also incorporated for adoption of TSTF-564. Chapter 15 was updated to support use of the "Infrequent Event" categorization for lost parts capable of causing high percentage of flow orifice blockage.
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ATTACHMENT A LaSalle County Station UFSAR Revision 24 Change Summary Report LUCR-0430 Incorporate Revision 1 of Regulatory Guide 1.71 "Welder Qualification for Areas of Limited Accessibility" Revised UFSAR Appendix 8, page 8.0-56 to indicate adoption of NRG RG 1.71 Revision 1.
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ATTACHMENT B LaSalle County Station FPR Revision 9 Change Summary Report
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LF2018-01 LF2018-01 revises LaSalle FPR Section H.3, page H.3-89-90, Table H.3-2 (sheet 9 of 22) for Fire Zone 4F3 replacing Ionization with Photoelectric.
The existing ionization detectors installed in the concealed cable space over the laboratories are obsolete. As a result. they are replaced with photoelectric detectors that are compatible with the new fire protection panel installed per EC 623230.
LF2019-01 LF2019-01 revises the FPR Section 3, "LASALLE COMPARISON TO 10CFR50 APPENDIX R" Pages 20, 42 and adds page 47 for NRC Endorsement of research position on current transformer, NUREG 7150 Vol 3, NUREG 7228 for circuit analysis conclusions.
LF2019-02 LF2019-02 revises the Fire Protection Report via EC 628041 which adds an additional Station Air Compressor to the Unit 2 Turbine Building. FPR Figure H.2-1 is revised to illustrate the addition SAC in Fire Zone SC 11.
Page 1 of 1
. ATTACHMENT C LaSalle County Station 10 CFR 50.59 Evaluation Summary Report L18-115. Re-Route of Line 2DG05A-4" This activity was a physical design change to modify and reroute Unit 2 Division 2 Core Standby Cooling System-Emergency Cooling Water System (CSCS-ECWS) pipeline 2DG05A-4".
Description of Activity:
The Division 2 pipeline 2DG05A-4" delivers cooling water from 2DG03A-10" within the Diesel Generator (DG) Building to Division 2 cubicle cooler 2VY03A in the Reactor Building (RB).
The existing pipeline was made of carbon steel and was routed underground between the Reactor and Diesel Generator Buildings. In order to eliminate the underground portion, this activity replaced 2DG05A-4" with stainless steel pipe routed indoors directly from the DG Building to the RB. The new routing passes through a new penetration from a Division 2 area in the DG Building to Division 1 Residual Heat Removal (RHR) Heat Exchanger "A" Cubicle (RHR "A" corner room). The new piping route passes through this corner room before entering
.the North general area of the Unit 2 RB Raceway, traveling from North to South along the raceway's West side, passing the Division 3 room cooler, and ending at the RHR 2B/C Pump Room Cooler (2VY03A). As part of the reroute of line 2DG05A-4" within the DG Building, this activity also removed previously disabled keep-fill lines 2DG80A-3/4" and 2RHL5A-3/4".
This activity also added new isolation valve 2DG118 to line 2DG05A-4" within the DG building
.upstream of the penetration into the RB. Once the tie-in to 2DG03A-1 O" was complete, the new isolation valve acted as the code boundary and allowed the 2A diesel cooling water pump to be placed back into service while work downstream of the isolation valve continued. This modification was installed online with the final tie-in to existing station piping occurring during an outage.
Summary of Conclusion for the Activity's 50.59 Review:
An adverse effect was evaluated regarding divisional separation due to routing the Unit 2 Division 2 CSCS-ECW line that supplies Division 2 cubicle cooler 2VY03A through areas that include Division 1 equipment and in the proximity to the Division 3 cubicle cooler 2VY02A. The new piping meets the design bases and regulatory bases for mechanical separation. There are no changes to plant operations, and no other changes to design bases or safety analyses descr:ibed -in the updated final safety analysis report (UFSAR). The replacement pipe was designed and installed seismically and to ensure the pipe os protected from fire, flooding, pipe whip, and missiles.
There are no changes made to the operation or control of the Division 1 RHR components, or the Division 2 CSCS-ECWS cooling flow to the Division 2 cubicle cooler. No new system interactions are created. There is no credible single failure that can affect both the Division 1 RHR heat exchanger and the rerouted Division 2 CSCS-ECW line. All items in the area are seismically supported. No pipes in the vicinity of the re-routed line meet the HELB definition in the UFSAR. There are no sources of internally generated missiles. This activity does not alter any SSCs with the potential to affect fission product barriers.
Page 1 of 6
ATTACHMENT C LaSalle County Station 10 CFR 50.59 Evaluation Summary Report L18-197. Temporary Change {TCC) #2-P229-18 to Support Maintenance Activities Related to Defeating/ Restoring Low Water Temperature Trip on Running Primary Containment Chillers
- The subject temporary change was installed to support maintenance activities until refueling outage L2R 17 to preclude spurious primary containment cooler compressor trips.
Description of Activity:
The Primary Containment Ventilation {VP) system is designed to maintain a suitable environment inside the drywell for equipment operation and equipment longevity. This is accomplished, in part, by providing chilled water that cools the drywell air. There are two chilled water loops, with each loop consisting of a circulating pump, a chiller unit evaporator and an expansion tank. Temporary Configuration Change (TCC) 2-P229-18 installed a jumper over Unit 2 "B" VP temperature switch 2TSL-VP910B to preclude spurious VP compressor trips, when the chiller outlet temperature could be too low. The function of the temperature switch is to prevent potentiaHy freezing up the output of the chillers. An operator special log was established to monitor the operating VP Chillers to ensure that the chilled water outlet temperature stayed above 37°F as recommended by the vendor.
The temporary change was installed to support maintenance activities until refueling outage L2R 17 to preclude spurious VP compressor trips. This period exceeds the 90-day timeframe that this TCC could be installed. Defeating the trips required operator action to monitor the chill water -outlet temperature, and to shut down the chiller if output temperature falls below the set"'point. Therefore, the activity involved a change to a procedure that adversely affected how UFSAR described design functions are performed or controlled.
Summary of Conclusion for the Activity's 50.59 Review:
The activity involved use of operator action to shut down the operating VP chiller in place of the automatic trip function of the chiller outlet temperature switches, The use of manual operator action to shut down an operating chiller does not.introduce the possibility of a change in the frequency of an accident because the failure of a VP chiller is not an initiator of any accident and no new failure modes are being introduced by the operator action. While the loss of drywell cooling can result in a plant transient such as a scram from high drywell pressure, the use of operator action to shut down the VP chiller when chill water temperature is trending too low will reduce the probability of a plant transient by maintaining more control over the transition from two chiller operation to one chiller operation or to shut down the operating chiller and place the standby chiller in service.
The actions required by operators are in controlled procedures that will be performed by trained operators. The timeframe of the monitoring is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the chill water outlet temperature is appropriate because the change in the temperature of the Service Water, which provides cooling to the VP chillers does not significantly change over an eight-hour
,period. The timeframe is also appropriate for performance of normal Operating Rounds of plant equipment. There is no likely error that can be made in the operator action of logging the chill water outlet temperature that can result in the malfunction of the operating VP chiller Page 2 of 6
ATTACHMENT C LaSalle County Station 10 CFR 50.59 Evaluation Summary Report since the activity is passive. The monitoring and use of the operator action to shut down a VP chiller when chill water temperature may trend too low does not impact other systems. The chiller will continue to operate as described in the UFSAR and other protective functions will ensure that the VP chiller will shut down if necessary.
L19-003. Methanol (MeOH) Injection for Unit,1 and Unit 2 Reactor Vessels During Initial Criticality Methanol Injection {MeOH) has been used as a method to mitigate lntergranular Stress Corrosion Cracking {IGSCC) during power operations by lowering system Electrochemical Corrosion Potential {ECP).
Description of Activity:
Hydrogen Water Chemistry {HWC), Noble Metals Chemical Coating Application (NMCA), and On-line Noble Chemistry {OLNC) have been effectively used in the General Electric boiling*
water reactor (BWR) fleet to mitigate IGSCC during power operations by lowering system .
ECP. Methanol Injection, a complement to existing technologies, would extend IGSCC mitigation to startup and shutdown periods when the reactor system is at intermediate temperatures, 200°F-535°F, where IGSCC initiation and crack growth rates are maximum.
Previous pilot demonstrations of MeOH injection provided evidence that MeOH drops the oxidant levels in reactor coolant below 25 ppb, with no traces of peroxides during sampling.
The L2R17 methanol demonstration confirmed the relationship between temperature, radiation, methanol-to-oxidant molar ratio, and ECP response. This established a dissolved oxygen criterion for IGSCC mitigation with MeOH injection at plant conditions where noble metal is applied. The activity injected methanol solution up to 400 ml/min, at 20% assays, not to exceed 75 gallons, during initial reactor vessel criticality and heat up for Unit 1 and Unit 2.
Summary of Conclusion for the Activity's 50.59 Review:
The pilot application of MeOH on Unit 1 was previously approved at a lower injection rate, 50ml/min for 25 gallons at 20% assay. The activity was evaluated as a new test or experiment in which the effects involve an SSC controlled in a manner that is outside the reference boµnds of the design for that SSC or inconsistent with analyses or description in the UFSAR. The bounding scenario of continuous MeOH injection upper limit demonstrated there was ,no .impact on the applicable Technical Requirements Manual 3.4.b, even though the conductivity limit in modes 2 and 3 of operations might be exceeded.
The assembly for MeOH injection, connected at the reactor building sample panel, became part of the plant SSC design, installed in accordance with design change EC 625060.
However, the design change activity was not adverse since it did not adversely affect the operation or performance of the sample panel or any safety-related functions, did not reduce the reliability of safety sec functions whose failure could initiate an accident or relax the manner in which Code requirements were met for interfacing SSCs or their design functions, nor introduced a new type of accident or malfunction with a different result, or change the existing UFSAR safety analyses, or element of an UFSAR described evaluation methodology, Page 3 of 6
ATTACHMENT C LaSalle County Station 10 CFR 50.59 Evaluation Summary Report or used an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses.
Safe operations are not compromised during normal plant operation, anticipated operational transients, or accident condition previously analyzed. No new accident conditions are introduced due to the injection of methanol. The frequency and consequences of accidents or likelihood of malfunctions are not increased. Fission product boundaries are not adversely affected.
L19-101, Operation of Both C VP Chillers with One Primary Containment Chilled Water Loop
- A new procedure was deyeloped to provide directions to operations staff in order to run one Primary Containment Chilled Water (PCCW) loop to operate both Units' "C" Primary Containment Ventilation (VP) Chillers. This capability provides redundancy for VP during a VP chiller maintenance window.
Description of Activity:
The PCCW system is not a safety-related system; therefore, it has no safety design bases.
The UFSAR describes Power Generation Design Bases as the design of the system as "the primary containment chilled water system for each Unit 1 and 2 consists of two chilled water circuits each comprised of one chilled water pump, one double-bu.ndle centrifugal chiller, and one drywell fan-coil unit." To achieve rated cooling capacity, a single-bundle chiller must be operated in parallel with the in-service double-bundle unit. The USFAR describes cooling for rated capacity as using a double bundled chiller ("A" or "B") and a single bundled chiller ("C").
The cooling capacity of a double bundled chiller is 550 tons and the cooling capacity of a single bundled chiller is 400 tons, for.a combination of 950 tons of cooling for rated capacity.
The new procedure aligns both units' single bundled chillers for a total of 800 tons of cooling capacity. This alignment is not described in the UFSAR, but provides adequate cooling for one unit's drywall with a lake temperature maximum design inlet temperature of 104° F. Use of this procedure removes one of the described back up chillers for the opposite unit modes of Operation, which is controlled administratively to restore operation as needed.
The USFAR describes having the ability to connect to a standby diesel generator during a loss
.of offsite power. The single bundled chiller units are powered from Bus 138 and Bus 231 X, which are not readily available to be powered from a diesel generator. However, power is lost to all the VP chillers and operations must manually load the VP chiller configuration required to be supplied from diesel generator. The way the diesel generator is used has not changed due to this activity.
Summary of Conclusion for the Activity's 50.59 Review:
This activity contained no physical change to an SSC that is an adverse change to the USFAR described design function. This activity provided a change to the procedure that controlled how the SSC design functions are performed or controlled. This alignment is not described in Page 4 of 6
ATIACHMENTC LaSalle County Station 10 CFR 50.59 Evaluation Summary Report the UFSAR, but provides adequate cooling for one drywell with a lake temperature maximum design inlet temperature of 104° F.
The two "C" chillers working in parallel can provide enough cooling capacity to handle the primary containment heat load, with margin. The equipment can be operated within the bounds of normal operating parameters that have been set by established procedures, but since the configuration is not described in the USFAR, the system interaction was reviewed as an adverse change. This Activity does not require a change to Technical Specifications.
L19-159 1 Tornado Missile Protection (TMPl Design for Compliance with Licensing Requirements This activity issued a design analysis to confirm that the tornado safe shutdown equipment list (TSSEL) conforms to the current design and licensing basis for tornado missile protection.
The purpose of tornado protection is to ensure the reactor can be brought to a safe and stable shutdown condition during or following a tornado event.
Description of Activity:
All nonconformances were evaluated using the Tornado Missile Risk Evaluator (TMRE) methodology delineated in NEI 17-02 "Tornado Missile Risk Evaluator (TMRE) Industry Guidance Document," revision 1A, including NRC limitations and exceptions that were addressed in revision 1B. Application of the TMRE methodology involved three major steps of (1) ,identification of SSCs that are not protected against tornado-generated missiles and missile characteristics, (2) determination of failure probabilities of the exposed SSCs important to safe shutdown using the Exposed Equipment Failure Probability {EEFP) calculation; and,
{3) calculation of applicable probabilistic risk assessment (PRA) metrics to ensure they do not exceed specified acceptance criteria from NRC Regulatory Guide 1.174. The TMRE method does not qualify the TSSEL; the TMRE analysis evaluated the risk metrics to show they meet requirements of NEI 17-02 Section 7 acceptance criteria.
Summary of Conclusion for the Activity's 50.59 Review:
The activity issued a design analysis to support the TMRE methodology implementation in accordance with the methodology delineated in NEI 17-02. The TMRE methodology used to evaluate and qualify the non-conformances was performed in accordance with NEI 17-02 guidance, which is not part of the station's current licensing basis. Therefore, the activity used an alternative evaluation methodology that is not part of the current UFSAR. Existing design analyses were not changed by this activity and continue to ensure equipment meets the current licensing bass and perform any UFSAR described functions. The activity did not involve a test or experiment. Adoption of the design analysis did not alter or modify any existing Technical Specifications or the Facility Operating License.
Page 5 of 6
ATIACHMENTC LaSalle County Station 10 CFR 50.59 Evaluation Summary Report L19-177, Impact Review of GEH GNF2 CAVEX35 Decay H~at and Radiation (EC 628805)
This activity increases the design basis End-of-Cycle (EOG) Core Average Exposure (CAVEX) for both units. The purpose of increasing the design basis CAVEX is to allow better utilization of nuclear fuels and improve fuel economy. The*increase in CAVEX provides the core designer flexibility to use fewer new fuel bundles (or lower enrichments) to achieve the desired operating cycle length.
Description of Activity:
The current analyzed EOG CAVEX for Global Nuclear Fuel 2 (GNF2) is increased from 33,370 Mega Watt Days per Short ton (MWd/ST) to 35,000 MWd/ST (CAVEX35) for decay heat and 41,000 MWd/ST for environmental qualification (EQ). CAVEX35 affected the decay heat and the source terms used in existing design analyses. The proposed activity includes re-analyzed radiological consequences for the design basis Loss of Coolant Accident (LOCA),
the Fuel Handling Accident (FHA), and the Control Rod Drop Accident (CRDA).
This activity did not physically modify or alter any design function or design limit for any SSC.
There was not *impact on the manner of plant operation or maintenance activity. Under the new analyses, instances where decay heat exceeds the existing analysis (i.e., from
. approximately 11 days to 31 years) have been reconciled in various calculations described in design analysis EC 628805.
Summary of Conclusion for the Activity's 50.59 Review:
The activity increased the CAVEX to 35,000 MWd/ST for decay heat and 41,000 MWd/ST for radiation, to allow better utilization of nuclear fuels and to improve fuel economy. There was no hardware change to any of the plant systems, and plant operations remained unaffected.
The fuel rods will continue to be operated below their mechanical and thermal design limits.
The activity did not adversely affect the design or safety function of any plant system or components.
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ATTACHMENT D LaSalle County Station 10 CFR.72.48 Evaluation Summary Report All 10 CFR 72.48 reviews performed from February 7, 2018 to March 12, 2020 were screenings. There were no 10 CFR 72.48 Evaluations performed during this period.
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ATTACHMENT E LaSalle County Station 10 CFR 54.37(b) Aging Management Review Summary In accordance with 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of the 10 CFR 54.37(b) for Holders of Renewed Licenses," the UFSAR update required by 10 CFR 50.71 must include any Structures, Systems or Components (SSCs) newly identified that would have been subject to an aging management review or evaluation -of time-limited aging analyses in accordance with 10 CFR 54.21. This UFSAR update must describe how the effects of aging will be managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation.
The 10 CFR 54.37(b) review of changes to the plant Current Licensing Basis covered the period of February 7, 2018 to January 8, 2020. The review included:
- Interviews of Program Managers/SME's,
- Engineering Changes that were installed or completed since the last UFSAR update,
- UFSAR pending change descriptions and revised text,
- NRC Interim Staff Guidelines (ISGs) related to license renewal, and
- Licensing Correspondence to and from the NRC.
No "newly identified" SSCs were identified that require aging management or evaluation of TLAA's in accordance with the License Renewal Rule. Therefore, there are no associated updates required to the LaSalle UFSAR and Aging Management Programs.
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ATTACHMENT F LaSalle County Station OSM Directory Structure
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001 LAS UFSAR Rev. 24 000 List of Effective Pages.pdf 434KB 001 LAS UFSAR Rev. 24 001 Chao 01 lntroduction.odf 255 KB 001 LAS UFSAR Rev. 24 002 Chao 02 Site Characteristics.odf 78227 KB 001 LAS UFSAR Rev. 24 003 Chao 03 Desian of Struct Como, Eauio.odf 39224 KB 001 LAS UFSAR Rev. 24 004 Chao 04 Reactor.odf 7289 KB 001 LAS UFSAR Rev. 24 005 Chap 05 Reactor Coolant.pdf 7680 KB 001 LAS UFSAR Rev. 24 006 Chap 06 Eng Safety Features.pdf 22467 KB 001 LAS UFSAR Rev. 24 007 Chao 07 Instr and Control Svs.odf 7368 KB 001 LAS UFSAR Rev. 24 008 Chap 08 Electric Power.pdf 3876 KB 001 LAS UFSAR Rev. 24 009 Chao 09 Auxiliarv Svstems.odf 1955 KB 001 LAS UFSAR Rev. 24 01 O Chap 09 Fiaures Part 1 of 7 .odf 2504 KB 001 LAS UFSAR Rev. 24 011 Chao 09 Figures Part 2 of 7.odf 92572 KB 001 LAS UFSAR Rev. 24 012 Chap 09 Figures Part 3 of 7.pdf 91863 KB 001 LAS UFSAR Rev. 24 013 Chao 09 Fiaures Part4 of 7.odf 80893 KB 001 LAS UFSAR Rev. 24 014 Chao 09 Fiaures Part 5 of 7.odf 70405 KB 001 LAS UFSAR Rev. 24 015 Chao 09 Fiaures Part 6 of 7.odf i 88351 KB 001 LAS UFSAR Rev. 24 016 Chao 09 Fiaures Part 7 of 7.odf 79382 KB 001 LAS UFSAR Rev. 24 017 Chao 10 Steam and Power Conv.odf 1034 KB 001 LAS UFSAR Rev. 24 018 Chao 11 Radioactive Waste Mamt.odf 1171 KB 001 LAS UFSAR Rev. 24 019 Chao 12 Radiation Protection.odf 10928 KB 001 LAS UFSAR Rev. 24 020 Chap 13 Conduct of Qperations.odf 425 KB 001 LAS UFSAR Rev. 24 021 Chap 14 Initial Test Program.odf 421 KB 001 LAS UFSAR Rev. 24 022 Chap 15 Accident Analvsis.odf 6058 KB 001 LAS UFSAR Rev. 24 023 Chap 16 Technical Soecifications.odf 417 KB 001 LAS UFSAR Rev. 24 024 Chap 17 Quality Assurance.odf 424KB 001 LAS UFSAR Rev. 24 025 Aooendices.odf 8300 KB 002 LAS FPR Rev. 9 001 LAS FPR Rev. 9.odf 15023 KB 003 LAS TRM . 001 LAS TRM.odf 5103 KB
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004LASTSB 001 LAS TSB.odf 2718 KB Page 1 of 1