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| {{Adams
| | #REDIRECT [[05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground]] |
| | number = ML24263A236
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| | issue date = 09/19/2024
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| | title = Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
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| | author name = Brown T
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| | author affiliation = Vistra Operations Company, LLC
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| | addressee name =
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| | addressee affiliation = NRC/NRR, NRC/Document Control Desk
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| | docket = 05000346
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| | license number = NPF-003
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| | contact person =
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| | case reference number = L-24-221
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| | document report number = LER 2021-001-01
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| | document type = Letter, Licensee Event Report (LER)
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| | page count = 1
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| }}
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| {{LER
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| | Title = Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000346
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| | LER year = 2021
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| | LER number = 1
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| | LER revision =
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:Davis-Besse Nuclear Power Station Terry J. Brown Site Vice President 5501 N. State Route 2 Oak Harbor, OH 43449 Office: 419 .321. 7676
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| L-24-221 September 19, 2024 10CFR50.73
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| ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
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| ==Subject:==
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| Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License Number NPF-3 Licensee Event Report 2021-001-01
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| Enclosed is Revision 01 to Licensee Event Report (LER) 2021-001, Emergency Diesel Generator Speed Switch Failure due to Direct Current System Ground. This event was initially reported pursuant to 10 CFR 50.73(a)(2)(i)(B). The LER is being revised to update the cause and corrective actions taken since the initial report submittal.
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| There are no regulatory commitments contained in this letter or its enclosure. The actions described represent intended or planned actions and are described for information only. If there are any questions or if additional information is required, please contact Mr. Robert W. Oesterle, Manager, Site Regulatory Compliance, at (419) 321-7462.
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| GMW
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| ==Enclosure:==
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| LER 2021-001-01
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| cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/3012027 (04-02 -2024) Estimated burden par response to comply \\I.1th this mandatay collection request 80 hours . Reported leS601lS LICENSEE EVENT REPORT (LER) llllmed a-e incaporalad nlD the icensing JroCeS& and fed bact kl ndustry. Send (;Of11ffl8fl1s regring blrden estimate b fie FOIA, lbary , IVld Information Serw:es lnncl1 (T-6 A10M), U . S. NuciM Regulatory (See Page 2 for required number of digits/characters for each block) Cornniasion, Washington, DC 20555-0001, or by e-mail to lnftx:olBcis.Resource@nrc.gov, and the 0MB 18\\'iewe,' at 0MB Office oflnformatiorl aid Regulab'y Affah, (3150-0104~ Attn: Desk Offloerforfle Nucea (See NUREG-1022, R.3 for instruction and guidance for completing this form Regulalory Commission, 7'1517lh Steel NW, Washington, OC 20503. The NRC may not oonduct or sponsor, http://www. nrc oov/readinq-rm/doc-collections/nuregs/staff/sr1022/r3D and a per$Oll is not *ed t> respond to, a collecllon of nmMion unless the document reques!lng or reqliring the oolleclion <il;plays a amnlly vaid otAl conlrol rurber .
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| : 1. Faclllty Name 181 050 2. Docket Number 3. Page Davis-Besse Nuclear Power Station, Unit 1 052 346 1 OF 5 4.
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| ==Title:==
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| Emergency Diesel Generator Speed Switch Failure due to Direct Current System Ground
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| : 5. Event Date 6. LER Number
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| * 7. Report Date 8. Other Facllltlea Involved Month Day Year Year Sequential Rev Month Day Year Faclllty Name 050 Docket Number Number No .
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| Facility Name Docket Number 02 12 2021 2021 - 001 - 01 09 19 2024 052
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| : 9. Operating Mode 10. Power Level 1 100
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| : 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 20.2203(a)(2)(vl) 60.73(a}(2)(ll)(A) D 50.73(a)(2)(vlll)(A) D 73.1200(a) 20.2201(b) 20.2203(a)(3)(i) 0 60.36(c)(1)(i)(A) 60.73(a)(2)(ii)(B) D 60.73(a)(2)(viii)(B) D 73.1200(b) 20.2201(d) D 20.2203(a)(3)(ii) 50.73(a)(2)(iii) D 50.73(a)(2)(ix)(A) D 73.1200(c) 20 .2203(8)(1) 20.2203(a)(4) D 50.36(c)(2) D 60.73(a)(2)(x) D 73.1200(d) -------------1.,..._-----------1 50.73(a)(2)(lv)(A) 20.2203(8)(2)(1) D 60.46(a)(3)(11) D 73.1200(e) 60.73(a)(2)(v}(A) 20.2203(a)(2)(ii) 0 21.Z(c) 0 60.69(g) 0 73.1200(f) D 60.73(a){Z)(v)(B) 73.n(a)(1) 20.2203(a)(Z)(iii) 50.73(a){2)(v)(C) 73. 77(a)(2)(1) 0 73.1200(g) 20.2203(a)(2)(Iv) 60.73(a)(2)(v)(D) 73. 77(a)(2)(ii) 0 73.1200(h) 20.2203(a)(2)(v) 0 50.73(a)(2)(I)(C) 60.73(a)(2)(vll)
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| D OTHER (Specify here, in abstract , or in NRC Form 366A) .
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| : 12. Licensee Contact for this LER Licensee Contact Phone Number (Include area code)
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| Gerald M. Wolf, Consulting Engineer, Regulatory Compliance (419) 321-8001
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| : 13. Complete One Line for Each Component Failure Described In this Report
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| ------------,-----------.------Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS B EK ST D283 y
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| : 14. Supplemental Report Expected Month Day Year
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| : 15. Expected SubmlHlon Date l8I No D Yes (If yes, complete 15. Expected Submission Date)
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| : 16. Abstract (Limit to 1326 spaces, i.e .. approximately 13 single-spaced typewritten lines)
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| On September 4 , 2020, with the Davis-Besse Nuclear Power Station operating at approximately 100 percent power, Emergency Diesel Generator (EDG) 2 failed to start during scheduled monthly surveillance testing. A failed speed switch was identified and replaced, restoring the EDG to Operable status on September 7, 2020. Based on a vendor analysis in conjunction with a review of applicable plant data, it was determined on February 12, 2021 that the speed switch was failed on September 1, 2020, due to a shorted component within the switch in conjunction with a ground on the station 125 VDC system .
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| Since the EOG was determined to be failed prior to discovery during routine monthly testing and the necessary Technical Specification actions for an inoperable EOG were not performed based on the time of failure, this event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B) as operation of the plant in a condition prohibited by the Technical Specifications. The cause of this event was less than adequate use of operating experience for the station DC distribution system, resulting in installation of EOG speed switches with components not rated for the maximum possible voltage. A new design of switch capable of withstanding the full voltage of the DC system was installed in January 2022.
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| NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04--02-2024) Estimated b urden per response to comp ly with this mandatory c ollection request 80 hours . Reported lessons learned a re ilcorporate d into the lice n sing process a nd fed b ack to industry. Send com ments
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| ,w.\\ LICENSEE EVE NT R E PO RT (L ER ) regarding bur den estimate to the FOIA, Library, an d In fo rmation Services Branch (T-6 A 10M). U . S.
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| ; i CO NTIN UATI O N S HEET Nucl ear Reg u la tory Com mission, wash lngto n, DC 20555--0001, o r by e-mai l to
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| \\;. I lnfocollects.Reso ur ce@nrc.gov, and the 0 MB reviewer a t 0MB Office o f Info rmation 111d Regu latory
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| ...... Affairs, (315~0104), Attn: Desk Officer fo r the Nuclea Reg~alD!y Commiss io n , 7251 7th Street NW ,
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| (See NUREG - 1022 , R.3 fo r instruction and gu idance for comp leting this form Wash ingto n, DC 20503. The NRC may not conduc1 or sponsor , and a person is no t required to http:/lwww.nrc .gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3D respond to, a collection of Information unless the document requesting o r requiring the collection displays a currently valid 0MB control number .
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| : 1. FACILITY NAME l8'J 050 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO.
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| Dav is-Besse Nuclea r Powe r Station Unit 1 346 2021 00 1 01 052
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| NARRATIVE
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| Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
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| System
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| == Description:==
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| The Davis-Besse Nuclear Power Station (DBNPS) Class 1 E Alternating Current (AC) Electrical Power Distribution System sources consist of the offsite power sources (preferred power sources, normal and alternate) and the two onsite standby Emergency Diesel Generators (EDGs) . An EOG [EK-DG] starts automatically on a Safety Features Actuation System (SFAS) [JE] actuation or on an essential bus degraded voltage or loss of voltage signal. After an EDG has started, it will automatically tie to its respective bus after offsite power is tripped.
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| The DBNPS Direct Current (DC) system [EJ] consists of two 250/125 Volt DC (VDC) motor control centers, four batteries, six battery chargers, four essential distribution panels, four 480V AC/125V DC rectifiers, and four nonessential distribution panels . The system is arranged to form two completely independent load groups . The DC system is des igned as an ungrounded system, so a single ground will not have an adverse impact on the DC system or individual components receiving power from the DC System . Each DC motor control center has a positive, a negative, and a neutral bus arranged to form a 250/125 VDC system; each bus is equipped with ground detection instrumentation that allows for identification and removal of a ground to prevent more significant issues.
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| Technical Specifications:
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| Technica l Specification (TS) Limiting Condition for Operation (LCO) 3 .8 .1.b requires two EDGs be Operable in Modes 1 through 4. With one EOG inoperable LCO 3.8 .1.b requires the following:
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| : 1. Surveillance Requirement 3.8.1.1 must be performed within one hour and at least once per 8 hours thereafter to verify correct breaker alignment and indicated power availability for each offsite circuit,
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| : 2. Any required feature(s) supported by the inoperable EDG must be declared inoperable when its redundant required feature(s) is inoperable within 4 hours from discovery,
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| : 3. The Operable EDG must be determined to be not inoperable due to common mode cause failure o r perform Surveillance Requirement 3.8.1.2 to verify the Operable EDG starts from standby conditions and achieves steady state voltage and frequency within 24 hours, and
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| : 4. Two EDGs must be restored to Operable status within 7 days or the plant must be in Hot Standby (Mode 3) within the next 6 hours and in Cold Shutdown (Mode 5) within the following 30 hours.
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| DESCRIPTION OF EVENT :
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| On September 4 , 2020, EDG 2 was declared inoperable and unavailable at 1112 hours for routine monthly testing to satisfy TS Surveillance Requirement 3.8.1 .2 . During the first idle start at 1134 hours, EDG 2 locked out on a failure to start. Due to work having been performed on the air start side that was being used to start the EOG, a second start attempt was performed on the opposite air start side, which also resulted in an EDG lock out on failure to start. Based on the observed indications from the second start attempt, the likely cause of the failure to start was suspected to be either the EDG speed switch [EK-ST] or magnetic pickup. Subsequent inspection of the EOG 2 speed switch identified internal overheating damage . The failed speed switch was replaced with the same model switch and the EDG tested satisfactorily, allowing the EOG to be declared Operable on September 7, 2020, at 1800 hours .
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| NRC FORM 366A (04-02-2024) Page 1 of§ NRC FORM 366A U.S. NUCLEAR REGULA TORY COMMISSION APPROVED BY 0MB: NO. 3160--0104 EXPIRES: 04/30/2027 (04-02 -2024) Estimated bur den per response to comply wilh this mandatory collection request: 80 hours . Reported
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| ,w., LI C EN SE E EVENT RE POR T ( L ER) lesso ns lea rned a re incor por ated Into the licensing process a n d fed bac k to industJy. Send com me nts regar ding bu rden estim ate to the FOIA, Libray, and Info rmation Service s Branc h {T -6 A 10M), U . S.
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| C t
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| ~ . CO NTI N U AT IO N SHEE T Nucl ea r Reg wtory Comm ission , W ashingto n , DC 20555-0001, o r by e-ma il to
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| ~ ~ lnfoco llects.Resour ce@ nr c .go v, an d the 0 MB reviewer a t: 0MB Off'1ee o f In form a tion and Reg u latory
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| ..... Affairs, (3150-0104), Attn: Desk Officer for the Nuclea- Reg ulatory Co mmission, 725 17th Street NW, (See NUREG -1 022 , R.3 fo r instruction and gu ida n ce for co m pleting this form W ashing ton , DC 20503. Th e NRC m ay not cond uct o r spo nso r, and a pe rso n is not required to http://www .nrc.gov/reading-rm/doc -collections/nuregs/staff/sr1022/r3D respond to, a co llection o f information u nless the do cu ment requ esting o r requimg the co llection displays a cu rrently valid 0 MB contr ol numbe r.
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| : 1. FACIL ITY NA ME 2. DOCKE T NUMBER 3. LER NUMBER
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| ~ 050 YEAR SEQUENTIAL REV Davis-Besse Nuclear Power Station Un it 1 NUMBER NO.
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| 346 2021 001 01 052
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| NARRATIVE
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| CAUSE OF EVENT:
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| The failed speed switch was installed in October 2019 as a ten-year preventive maintenance act ivity. The switch installed was a different part from a different manufacturer as the previous sw itch was obsolete and no longer available . Due to the short period of time between installation and failure, the failed speed switch was shipped to an external vendor, whose inspection revealed excessive damage at the input power section of the speed switch.
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| Based on the vendor's conclusion that the failure may have been related to the power supplied to the speed switch, a review of the DBNPS 125 VDC system history was performed . This review, completed on February 12, 2021, identified a hard ground had been received on Direct Current Motor Control Center (DCMCC) 2 [EJ-MCC] on August 25, 2020. Troubleshooting of this ground commenced later that day. On September 1, 2020, the breaker
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| [BQ-BKR] for the High Pressure Injection Pump 2 DC oil pump motor was opened at approximately 1500 hours as part of these troubleshooting efforts, resulting in the ground switching from a hard ground to an oscillating ground.
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| This oscillating ground condition cleared when the EOG 2 speed switch was removed on September 5, 2020 ,
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| following the failure during testing.
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| The cause of the failed EOG 2 speed switch was initially determined to be a shorted component within the speed switch concurrent with a ground on the 125 VDC power supply to the speed switch, resulting in failure of the switch.
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| With two competing grounds it was postulated there was sufficient direct current flow to cause the damage identified in the speed switch. Neither of the grounds on the 125 VDC system led plant personnel to conclude that any plant equipment had failed as a result of the grounds , and the speed switch was not known to be failed until regularly scheduled testing was performed.
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| In July 2021 it was identified that the EOG speed switch design installed in October 2019 utilized an auxiliary circuit board that contains electromagnetic and radio frequency interference (EMI/RFI) filtering and surge suppression devices at the DC input. This circuit contained a metal oxide varistor (MOV) that connected to the 125 VDC positive inlet terminal and station ground. This MOV had a maximum continuous rating of 170 VOC. Since the DC System includes a continuous ground monitor that connects the neutral and negative rails to station ground through resistors and an ammeter , the arrangement of the ground detector resulted in the positive 125 VDC terminal of the speed switch to see +200 VDC to ground . This overvoltage condition likely resulted in a decreased life of the MOV.
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| The Root Cause of this event was less than adequate incorporation, internalization, and anchoring of operating and in-house experiences as it pertains to the unique design vulnerabilities in the DBNPS DC distribution system. A similar issue occurred in 2010 when a component was installed onto the DC system but was not rated for the conditions present within the system. Because learnings from the previous incident were not anchored into any design documents or specifications, when replacing the EOG speed switches the station failed to select equipment that was suitable to function in the DC system .
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| ANALYSIS OF EVENT:
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| A qualitative risk assessment was performed for the approximately six days EOG 2 was unavailable, starting with the initiation of the oscillating ground on September 1, 2020 , at approximately 1500 hours, and ending with EOG 2 becoming available following completion of testing on September 7 at approximately 1600 hours. During this time period, all redundant train 1 equipment remained Operable, and no risk-significant equipment in train 2 was unavailable or inoperable . The plant risk associated with the extended unavailability of EOG 2 for less than the 7-day Completion Time of TS LCO 3.8 . 1 Required Action B .4 is considered to be of very low safety significance.
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| NRC FORM 366A (04-02-2024} Page 1 of~
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| NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per respoose to comply with this mandato!y collection request: 80 hours . Reported
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| lessons learned are incorporated ilto the licenslng process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the FOIA, U>rary , and Information Services Branch (T-6 A tOM), U . S.
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| CONTINUATION SHEET Nuclear Regu latory Commission , Washington , DC 20555-0001, or by e-mal l to lnfocollects.Resovrce@nrc .gov , and the 0MB reviewer at: 0MB Office of Information and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission , 7'25 17th Street NW ,
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| (See NUREG-1022, R.3 for instruction and guidance for completing this form Washington , DC 20503. The NRC may not conduct or sponsor , and a person is not required to http://www.nrc.gov/readinq-rm/doc-collections/nuregs/staff/sr1022/r3D respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number.
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| : 1. FACILITY NAME 181 050 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV Davis-Besse Nuclear Power Station Unit 1 NUMBER NO.
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| 346 2021 001 01 052
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| NARRATIVE
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| Reportability Discussion :
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| When the EOG 2 speed switch was initially discovered failed following the unsuccessful test start on September 4, 2020, there was no firm evidence at that time that the switch had failed prior to the test, so the failure was assumed to be at the time of discovery in accordance with NRC reporting guidance contained in NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 50.73, Revision 3. Following receipt of the vendor's evaluation of the failed switch and further review of the DBNPS 125 VDC System history, it was determined EOG 2 was inoperable prior to the start of the September 4, 2020, monthly test. EOG 2 was determined to be inoperable for approximately three days with the plant operating in Mode 1 prior to it being declared inoperable and unavailable on September 4, 2020, at 1112 hours for monthly testing. Because Technical Specification 3.8.1 requires actions to be taken within 1 hour for an inoperable EOG, this issue represents operation of the plant in a condition prohibited by the plant's Technical Specifications, which is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B). Revision 00 of this Licensee Event Report was submitted 60 days from the discovery of the reportable issue on February 12, 2021, in accordance with 10 CFR 50.73(a)(1). Because all redundant train 1 equipment remained Operable during the time EOG 2 was inoperable, no loss of Safety Function per 10 CFR 50 .73(a)(2)(v) occurred .
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| When Surveillance Requirement 3.8.1. 1 was performed within one hour of declaring EDG 2 inoperable on September 4, no issues were identified with the offsite circuit breaker alignments and power availability. EDG 1 was successfully idle started on September 5 at 0900 hours in accordance with Surveillance Requirement 3.8.1.2 to satisfy LCD 3.8.1 Action 8.3.1 to verify it was not inoperable due to a potential common cause failure. EOG 2 was subsequently restored to Operable status within the seven days allowed by LCO 3.8.1 Action B.4.
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| CORRECTIVE ACTIONS:
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| Completed Actions:
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| The ground on the High Pressure Injection Pump 2 DC oil pump motor was repaired on September 3, 2020, by repairing the damaged wire to the motor .
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| A replacement speed switch of the same model was installed and post maintenance testing was completed satisfactorily at 1600 hours on September 7, 2020, allowing EOG 2 to be declared Operable at 1800 hours.
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| Upon identification of the vulnerability of the installed speed switches to a higher than design voltage, a Standing Order was issued to the operators with guidance to more readily identify grounds that could affect the EDG speed switches.
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| The EOG speed switches were replaced in January 2022 with a model using an external power supply and capable of withstanding full voltage within the DBNPS DC Ground Detection System.
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| The DC System voltage to ground configuration was added to the DC electrical distribution system of the station Design Criteria Manual as well as appropriate DC system specifications and DC system descriptions.
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| NRC FORM 366A (04-02-2024) Page ~of.§ NRC FORM 366A U.S. NUCLEAR REGULA TORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per response to comply with this mandatory collection request: 80 hours . Reported
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| ~- ..... ~ LICENSEE EVENT REPORT (LER) lessons learned ere incorporated into the licensing process and fed back to industry. Send comments l~~ regarding burden estinate to the FOIA, Library, and Information Sel\\lices Branch (T-6 A10M), U . s.
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| ~~! CONTINUATION SHEET Nuclear Regulatory Commission , Washington , DC 20555-0001, or by e-mai l to
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| \\;~ ~ lnfocollecis.Resource@nrc.gov, and the 0MB reviewer at 0MB Office of Information c11d Regulatory
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| ...... Affars, (3150-0104), Attn: Desk Officer for the Nuclear Reg~atory Commission , 725 17th Street NW, (See NUREG - 1022, R.3 for instruction and guidance for completing this form Washington, DC 20503. The NRC may not conduct or sponsor , 111d a person is not required to http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/QO respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number.
| |
| : 1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER 050 YEAR SEQUENTIAL REV Davis-Besse Nuclear Power Station Unit 1 NUMBER NO.
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| 346 2021 001 01 052
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| NARRATIVE
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| Scheduled Actions:
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| No further actions are planned.
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| PREVIOUS SIMILAR EVENTS:
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| LER 2010-003 dated October 15, 2010, documents an event where a train of Auxiliary Feedwater was inoperable for longer than allowed by the TS LCO due to a ground in the DC system that was not adequately prioritized for identification and repair. The Auxiliary Feedwater Pump discharge control solenoid valve position controller board was designed for up to 140 voe .
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| NRC FORM 366A (04-02-2024) Page.§ of.§
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| }}
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| {{LER-Nav}}
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