05000335/LER-2019-002, Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip
| ML19309E532 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/05/2019 |
| From: | Deboer D Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2019-193 LER 2019-002-00 | |
| Download: ML19309E532 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(ix)(A) 10 CFR 50.73(a)(2)(i) |
| 3352019002R00 - NRC Website | |
text
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:
St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 2019-002-00 Date of Event: September 7, 2019 NOV 0 5 2019 L-2019-193 10 CFR 50.73 Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip Licensee Event Report 2019-002 is being submitted pursuant to the requirements of 10 CFR 50. 73 to provide notification of the subject event.
Respectfully, Daniel DeBoer Site Director St. Lucie Plant DD/kp 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 APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
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LICENSEE EVENT REPORT (LER)
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- 3. PAGE St. Lucie Unit 1 05000335 1 OF 3
- 4. TITLE Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR n/a 05000 FACILITY NAME DOCKET NUMBER 9
7 2019 2019 -
002 - 00 11 5
2019 n/a 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 D 20.2201 (d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50. 73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 5o.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1 )(i)(A)
~ 50. 73(a)(2)(iv)(A)
D 50. 73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1 )(ii)(A)
D 50. 73(a)(2)(v)(A)
D 73.71 (a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50. 73(a)(2)(v)(B)
D 73.71 (a)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50. 73(a)(2)(v)(C)
D 73.77(a)(1) 100 D 20.2203(a)(2)(v)
D 50. 73(a)(2)(i)(A)
D 50. 73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50. 73(a)(2)(i)(B)
D 50. 73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
- 6. LER NUMBER I
SEQUENTIAL I NUMBER 002 REV NO.
00 An extent of condition review of potentially susceptible cooling water piping as identified in the root cause evaluation has been performed for all motors except Unit 2 RCP motors with no findings. The extent of condition of Unit 2 RCP cooling water piping will be performed in the next Unit 2 refueling outage.
Safety Significance
The Reactor Coolant Pump trip initiated a Reactor Coolant System low flow actuation in the Reactor Protection System resulting in an automatic reactor trip, which is an analyzed event in the Updated Final Safety Analysis Report (UFSAR). All control element assemblies (CEAs) fully inserted into the core and the trip was uncomplicated with all safety functions satisfied. The plant was stabilized in Mode 3 hot standby conditions.
The event did not impact the environment and there were no radiological or security related implications.
Therefore, this event had no impact on the health and safety of the public.
Corrective Actions
- 1.
The 1A1 RCP motor was replaced.
- 2. An extent of condition review of potentially susceptible cooling water piping as identified in the root cause evaluation has been performed for all motors except Unit 2 RCP motors with no findings.
The following planned corrective actions are being tracked in the St. Lucie Corrective Action Program (CAP):
- 1.
Revise specification, SPEC-E-008, FPL FLEET MOTOR REPAIR/REFURBISHMENT/ REWIND REQUIREMENTS SPECIFICATION, to clarify that Appendix A, MOTOR REPAIR REQUIREMENTS FORM, is not intended, and shall not be used, to contract for work or services beyond the defined scope in the specification (i.e., code piping work, cabling work, engineering design services, shall not be performed).
Scope beyond that defined in SPEC-E-008 shall be contracted under a separate specification, scope of work, or purchase document developed by qualified individuals using the applicable governing FPL procedures.
- 2.
Seal penetrations in the Unit 1 and Unit 2 RCP motor enclosures to restore NEMA MG-1 drip proof ratings.
- 3.
Perform extent of condition review of Unit 2 RCP cooling water piping configurations during the next Unit 2 refueling outage.
Failed Components Identified Tags: MOTOR, RCP Manufacturer: Allis Chalmers Model No.: ANVWG (6500)
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