05000335/LER-2012-005-01, Regarding Reactor Trip on Turbine Trip

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Regarding Reactor Trip on Turbine Trip
ML12341A235
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 11/26/2012
From: Jensen J
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2012-402 LER 12-005-01
Download: ML12341A235 (4)


LER-2012-005, Regarding Reactor Trip on Turbine Trip
Event date:
Report date:
Reporting criterion: 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)

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
3352012005R01 - NRC Website

text

FPL.

November 26, 2012 L-2012-402 10 CFR 50.73 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 2012-005-01 Date of Event: June 2, 2012 Unit 1 Reactor Trip on Turbine Trip The attached supplement to Licensee Event Report 2012-005 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Additionally, this Licensee Event Report was originally submitted per letter, L-2012-291, with an incorrect sequence number of 2012-007. The correct sequence number is 2012-005. This administrative error has been corrected and was discussed with NRR Project Manager, Tracy J.

Orf, St. Lucie Plant Licensing Branch 11-2.

41ce President St. Lucie Plant JJ/rcs Attachment 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: 10/31/2013

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

St. Lucie Unit 1 05000335 1 OF 3

4.

TITLE Unit 1 Reactor Trip on Turbine Trip

5.

EVENT DATE

6.

LER NUMBER T 7.

REPORT DATE

8.

OTHER FACILITIES INVOLVED SEQUENTIA REV I

FACILITY NAME DOCKET MONTH DAY YEAR YEAR I MONTH DAY YEAR NA NUMBER 6

02 2012 2012 -

005 01 I 11 26 12 FACILITY NAME DOCKET NUMBER

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii) 1 E

20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

[j 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

[I 20.2203(a)(4)

[I 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

_[

20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

[I 50.73(a)(2)(ix)(A)

10. POWER LEVEL [3 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

ED 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

[: 73.71 (a)(4) 100%

El 20.2203(a)(2)(iv)

[3 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B)

El 73.71(a)(5)

El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

[E 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D)

Specify in Abstract below or in

Corrective Actions

The corrective actions below have been entered into the site corrective action program.

Any changes to the actions will be managed under the corrective action program.

1. Additional guidance has been added to the annunciator response procedure for responding to TCS alarms.
2.

A new normal operating procedure was developed and implemented for the TCS.

3. Additional TCS training is being provided to Operations, Engineering, and Maintenance.
4.

New maintenance procedures were developed and implemented for the TCS.

5.

The design control process is being revised to require risk based reviews for post maintenance test sequencing following risk significant plant modifications.

Similar Events

A search of the corrective action database for three years was performed and identified no issues that were related to the faults identified with this event.

Failed Component(s)

The primary controller (Drop 53) failed due to a fault in the Remote Node Controller or the Media Attachment Unit.

The back up controller (Drop 3) failed due to a failed fiber optic cable field connector.

Manufacture:

Model:

Emerson Electric Company IC31203G01, Ovation RNC Electronics Module IC31204G01, Ovation RNC Personality Module IC31179G02, Ovation MAU Electronics Module IC31181G02, Ovation MAU Personality Module