05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly
| ML22063A075 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/04/2022 |
| From: | Deboer D Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2022-024 LER 2022-001-00 | |
| Download: ML22063A075 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) |
| 3892022001R00 - NRC Website | |
text
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re:
St. Lucie Unit 2 Docket No. 50-March 4, 2022 Reportable Event: 2022-001-00 Date of Event: January 6, 2022 L-2022-024 10 CFR 50.73 Reactor Shutdown Required by Technical Specifications due to a Misaligned Control Element Assembly The attached Licensee Event Report 2022-001 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Respectfully,
()JOA-Daniel DeBoer Site Vice President St. Lucie Plant DD/res Attachment cc:
St. Lucie NRC Senior Resident Inspector St. Lucie NRC Program Manager Florida Power& Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023 LICENSEE EVENT REPORT (LER)
(See Page 3 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 1. Facility Name St. Lucie Unit 2
- 2. Docket Number 05000389
- 3. Page 1 of 3
- 4. Title Reactor Shutdown Required by Technical Specifications due to a Misaligned Control Element Assembly
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Revision Number Month Day Year Facility Name n/a Docket Number 05000 01 06 2022 2022 -
001 - 00 03 04 2022 Facility Name n/a Docket Number 05000
- 9. Operating Mode 1
- 10. Power Level 68%
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 10 CFR Part 20 20.2203(a)(2)(vi) 50.36(c)(2) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2201(b) 20.2203(a)(3)(i) 50.46(a)(3)(ii) 50.73(a)(2)(v)(A) 10 CFR Part 73 20.2201(d) 20.2203(a)(3)(ii) 50.69(g) 50.73(a)(2)(v)(B) 73.71(a)(4) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C) 73.71(a)(5) 20.2203(a)(2)(i) 10 CFR Part 21 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D) 73.77(a)(1) 20.2203(a)(2)(ii) 21.2(c) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 73.77(a)(2)(i) 20.2203(a)(2)(iii) 10 CFR Part 50 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 73.77(a)(2)(ii) 20.2203(a)(2)(iv) 50.36(c)(1)(i)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(v) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
OTHER (Specify here, in abstract or in NRC 366A)
- 12. Licensee Contact for this LER Licensee Contact Richard Sciscente, Licensing Engineer Telephone Number (Include area code)
(772) 467-7156 Cause System Component Manufacturer Reportable To IRIS
Cause
System Component Manufacturer Reportable To IRIS X
AA MO W120 Y
- 14. Supplemental Report Expected YES (If yes, complete 15. Expected Submission Date)
NO
- 15. Expected Submission Date Month Day Year Abstract (Limit to 1560 spaces, i.e., approximately 15 single-spaced typewritten lines)
On January 6, 2022 at 1937 EST with Unit 2 in Mode 1 at 68% power, the reactor was manually shutdown as required by Technical Specification Action Statement 3.1.3.1.e, due to Control Element Assembly (CEA) #27 misaligned from its CEA Group and unable to be realigned with its group within prescribed time limits.
Initial troubleshooting determined that the direct cause was a malfunction of the CEA #27 Control Element Drive Mechanism (CEDM) motor. The #27 CEDM motor was replaced while Unit 2 was in Mode 5.
Reactor shutdowns are analyzed events in the Updated Final Safety Analysis Report. The shutdown was uncomplicated. Therefore, this event had no impact on the health and safety of the public.
Page 3 of 3 Failed Components Identified
- 1) CEDM #27 motor
Description
CEDM magnetic jack assembly Part Number: E-13172-163-001-1
Description
CEDM motor assembly Part Number: SCEDM-163-202 Serial Number: N4720 S/N 158 Manufacturer: Westinghouse
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