05000266/LER-2016-002, Regarding Operation or Condition Prohibited by Technical Specifications
| ML16152A094 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/31/2016 |
| From: | Coffey B Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2016-0024 LER 16-002-00 | |
| Download: ML16152A094 (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)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2662016002R00 - NRC Website | |
text
ENERGY May 31,2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 1 Docket 50-266 Renewed License No. DPR-24 Licensee Event Report 266/2016-002-00 Unit 1 Operation or Condition Prohibited by Technical Specifications POINT BEACH NRC 2016-0024 10 CFR 50.73 Enclosed is Licensee Event Report (LER) 266/2016-002-00 for Point Beach Nuclear Plant, Unit 1. NextEra Energy Point Beach, LLC is providing this LER to report an operation or condition prohibited by Technical Specifications.
This letter contains no new regulatory commitments.
If you have any questions please contact Mr. Bryan Woyak, Licensing Manager, at 920/755-7599.
Sincerely, NextEra Energy Point Beach, LLC Bob Co y
Site Vice President Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 1013112018 (11-2015)
~~t..,J)-P.REO(r~
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Point Beach Nuclear Plant Unit 1 05000266 1 OF 3
- 4. TITLE Operation or Condition Prohibited by Technical Specifications
- 5. EVENT DATE
- 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 NA 05000 FACILITY NAME DOCKET NUMBER 04 01 2016 2016 - 002 00 05 31 2016 NA 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)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
ALL D
D D
D 50.73(a)(2)(ix)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii)
D 20.2203(a)(2)(i)
D 50.36(c)(1 )(i)(A)
D 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)
ALL 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)
~ 50.73(a)(2)(i)(B)
D
- 50. 73(a)(2)(vii)
D 73.77(a)(2)(ii)
... :*:, *. ?'L.r***.. *.x.. ~*~~~
D
- 50. 73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
Corrective Actions
05000266 YEAR 2016 SEQUENTIAL NUMBER 002 REV NO.
00 The 1X-03 transformer differential current relay wiring error has been corrected. A corrective action has been created from the extent of condition review of work performed by contractors to enhance the contractor training on the proper use of plant processes for lifting and landing wires/leads on equipment.
Similar Events
There have not been similar events of this condition prohibited by technical specifications reported in the past three years.
Component Failure Data
None Description of the Event:
SEQUENTIAL NUMBER 002 REV NO.
00 At 1132 On April 1, 2016 the 345/13.8kV high voltage station auxiliary transformer (1X-03) tripped on a differential current relay (1-87 NX-03) actuation. Review of this event determined that there were three instances over the past three years when the required action completion time for not satisfying the Limiting Conditions For Operation of Technical Specification 3.8.1 (AC Sources-Operating) and 3.8.2 (AC Sources-Shutdown) would have been exceeded with the latent error present.
This 60 day licensee event report is being submitted in accordance with the requirements of 10 CFR 50.73(a)(2)(i)(B).
Cause of the Event
The cause of the operation or condition prohibited by technical specifications has been determined to be a wiring error introduced on April 3, 2013.
Analysis of the Event
The 345/13.8kV high voltage station auxiliary transformer (1X-03) tripped on a differential current relay (1-87 NX-03) actuation while starting a Reactor Coolant Pump motor. The actuation triggered a 1X-03 lockout. During the event, an automatic fast bus transfer occurred as designed powering the 13.8kV/4.16kV low voltage station auxiliary transformer ( 1 X-04) from offsite power through the opposite unit 345/13. 8kV high voltage station auxiliary transformer (2X-03). An under voltage condition was not detected on the downstream 4.16kV safeguard bus switchgear (1A-05 or 1A-06) that would have started the emergency diesel generators. Operations promptly restored equipment affected by the 1X-03 lock out, including station battery chargers (D-07 and D-108) within four minutes. The 1X-04 transformer was returned to service through the 1 X-03 transformer at 2342 on April 1, 2016.
An event investigation team determined the cause of the event to be a wiring error associated with the differential current relay. With the wiring error present, actuation of the relay was dependent upon the loading of the transformer.
As transformer load would increase, the relay would get closer to its actuation. If the relay actuated, the 1X-03 transformer would lock out and remove the circuit from the offsite transmission network. This is what occurred during the April 1, 2016 event.
Technical Specification 3.8.1 requires the associated unit X-03 transformer to be operable. Technical Specification 3.8.2 requires an offsite circuit to be operable. Analysis of the 1X-03 transformer load data for the past three years determined there were three instances when the required action completion time for not satisfying the Limiting Conditions For Operation of Technical Specification 3.8.1 and 3.8.2 would have been exceeded.
Safety Significance
The condition was determined to be of very low safety significance. If the condition would have presented itself, Operations would have promptly restored equipment affected by the 1X-03 lock out. If an under voltage condition would have been detected on the downstream 1A-05 or 1A-06, the emergency diesel generators would have started and powered safety systems, structures or components needed to shut down the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material or mitigate the consequences of an accident. There was no impact on the health and safety of the public as a result of this condition.
Corrective Actions
05000266 YEAR 2016 SEQUENTIAL NUMBER 002 REV NO.
00 The 1X-03 transformer differential current relay wiring error has been corrected. A corrective action has been created from the extent of condition review of work performed by contractors to enhance the contractor training on the proper use of plant processes for lifting and landing wires/leads on equipment.
Similar Events
There have not been similar events of this condition prohibited by technical specifications reported in the past three years.
Component Failure Data
None