L-2024-112, Condition Prohibited by Technical Specifications
| ML24193A211 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/10/2024 |
| From: | Rasmus P Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-2024-112 LER 2024-002-01 | |
| Download: ML24193A211 (1) | |
Text
- FPL..
July 10, 2024 L-2024-112 10CFR50.73
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Re: Turkey Point Unit 3 Docket No. 50-250 Reportable Event: 2024-02 Date of Event: February 20, 2021
Condition Prohibited by Technical Specifications
The attached Licensee Event Report 2024-02-01 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Respectfully,
Pau1~s ~ ~
General Manager - Regulatory Affairs Florida Power & Light Company
Attachment
cc: Turkey Point NRC Senior Resident Inspector Turkey Point Station NRC Program Manager
Florida Power & Light Company
9760 SW 344th Street, Homestead, FL 33035 NRC FORM 366 U.S. NUCLEAR REGULATORY 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 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons
~"*E4~ learned are incorporated into the licensing process and fed back to in dustry. Send comments regarding burden
/¥\\ LICENSEE EVENT REPORT (LER ) estimate to the FOIA, Library, and In formation Collections Branch (T-6 A10M), U. S. Nuclear Regulatory and the 0MB reviewer
\\ iJ -... I'..... (See Page 2 for required number of digits/characters for each block) Commission, Washington, DC 20555-0001, or by email to lnfocollects.Resource@nrc.gov, at 0MB Office of In formation and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory or spcnsor, and a person is (See NUREG-1022, R.3 for instru ction and guidance for complet ing this form Commission, 725 17th Street NW, Washington, DC 20503. The NRG may not conduct blt1r /lwww m:i; go'llreadiag-cmidoc-collectioaslauregs /s!affllicl Q22/Ql) not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number.
- 1. Facility Name 00 050 2. Docket Number 3. Page
Turkey Point Unit 3 D 052 00250 1 OF 2
- 4. Title
Condition Prohibited by Technical Specifications
- 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Involved
Month Day Year Year Sequential Rev isio n Month Day Year Facility Name D Docket Numb er Number No. 050
Docket Number 02 07 2021 2024 - 002 - 01 07 10 2024 Facility Name D 052
- 9. Operating Mode 11~. Power Level 1 100
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR § : (Check all that apply)
10 CFR Part 20 D 20.2203(a)(2)(vi) 10 CFR Part 50 D 50. 73(a)(2)(ii)(A) D 50. 73(a)(2)(viii)(A) D 73.1200(a)
D 20.2201(b) D 20.2203(a)(3)(i) D 50.36(c)(1 )(i)(A) D 50. 73(a)(2)(ii)(B) D 50. 73(a)(2)(viii)(B) D 73.1200(b)
D 20.2201(d) D 20.2203(a)(3)(ii) D 50.36(c)(1 )(ii)(A) D 50.73(a)(2)(iii) D 50. 73(a)(2)(ix)(A) D 73.1200(c)
D 20.2203(a)(1) D 20.2203(a)(4) D 50.36(c)(2) D 50. 73(a)(2)(iv)(A) D 50. 73(a)(2)(x) D 73.1200(d)
D 20.2203(a)(2)(i) 10 CFR Part 21 D 50.46(a)(3)(ii) D 50.73(a)(2)(v)(A) 10 CFR Part 73 D 73.1200(e)
D 20.2203(a)(2)(ii) D 21.2(c) D 50.69(9) D 50.73(a)(2)(v)(B) D 73.77(a)(1) D 73.1200(f)
D 20.2203(a)(2)(iii) D 50. 73(a)(2)(i)(A) D 50. 73(a)(2)(v)(C) D 73. 77(a)(2)(i) D 73.1200(9)
D 20.2203(a)(2)(iv) [Z] 50. 73(a)(2)(i)(B) D 50. 73(a)(2)(v)(D) D 73. 77(a)(2)(ii) D 73.1200(h)
D 20.2203(a)(2)(v) D 50. 73(a)(2)(i)(C) D 50.73(a)(2)(vii)
D OTHER (Specify here, in abstract, or NRC 366A).
- 12. Licensee Contact for this LER
Licensee Contact Phone Number (Include area code)
Bob Murrell, Licensing Engineer 319-651-9496
- 13. Complete One Line for each Component Failure Described in this Report
Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS B BP V NIA y
- 14. Supplemental Report Expected Month Day Year
- 15. Expected Submission Date
[Z] No Yes (If yes, complete 15. Expected Submission Date) D
- 16. Abstract (Limit to 1326 spaces, i.e., approximately 13 single-spaced typewritten lines)
This LER Revision supersedes LER 2024-002-00 in its entirety.
On February 7, 2021, while in Mode 1, valve 3-759A, 3A Residual Heat Removal Heat Exchanger Outlet Isolation Valve was discovered to have a deficient reach rod gearbox causing it to become inoperable. Due to an incorrect interpretation of Technical Specifications (TSs), the station did not recognize that LCO 3.5.2.e, which requires two flow paths capable of taking suction from the containment sump, was not met, and therefore did not enter TSAS 3.5.2.a. This action r equires restoring the inoperable component to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Contrary to this requirement, a condition prohibited by TS occurred on February 11, 2021. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pursuant of 10 CFR S0.73(a)(2)(i)(B), Condition Prohibited by TS.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per response lo comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are in corporated into lhe licensing process and fed back to industry. Se nd comments LICENSEE EVENT REPORT (LER) regarding burden estimate lo the FOIA, Library, and Information Collections Branch (T-6 A10M), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to CONTINUATION SHEET lnfocollects.Resource@nrc.gov, and the 0MB reviewer al: 0MB Office of Information and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission, 72517th Street NW, (See NUREG-1022, R.3 for instruction and guidance for completing this form Washington, DC 20503. The NRG may not conduct or sponsor, and a person is not required to http :1/www nrc.gov/readjng-rm/doc-collections/nuregs/staff/sr1022/r3D respond to, a collection of information unless the document requesting or requiring the co ll ection displays a currently valid 0MB control number.
- 1. FACILITY NAME 050 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO.
!Turkey Point Unit 3 052 00250 I 02 I I 2024 I - -
I~ I 0
NARRATIVE
Description of Event: I
On February 7, 2021, while in Mode 1, valve 3-759A, 3A Residual Heat Removal Heat Exchanger Outlet Isolation Valve was discovered to have a deficient reach rod gearbox causing it to be inoperable. At the time, due to an incorrect interpretation of Technical Specifications (TSs), the station did not recognize that LCO 3.5.2.e which requires two flow paths capable of taking suction from the containment sump was not met, therefore did not enter TS Action Statement 3.5.2.a. This action requires restoring the inoperable component to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in hot shutdown w ithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Contrary to this requirement, a condition prohibited by TS occurred on February 11, 2021.
Cause of Event:
Incorrect interpretation of TS.
Safety Significance :
Valve 3-759A is a back-up to Motor Operated Valve (MOV) 3-744A, which remained operable during the time 3-759A was inoperable, therefore, there was no actual safety significance related to this event. This event did not prevent any safety systems from performing their safety related functions.
This event is being reported pursuant of 10 CFR 50. 73(a)(2)(i)(B), Condition Prohibited by TS.
This event did not result in a Safety System Functional Failure.
Corrective Actions:
Valve 3-759A was repaired and restored to operable status on March 9, 2023.
Similar Events :
A review of events over the past 5 years did not identify any previous events that involved the same underlying cause of the event reported under this Licensee Event Report.
NRG FOR M 366A (04-02-2024) Page 2 of 2